Procedures for evaluation of vibratory ground motions of soil deposits at nuclear power plant sites

International Nuclear Information System (INIS)

1975-06-01

According to USNRC requirements set forth in Appendix A, 10 CFR, Part 100, vibratory ground motion criteria for a nuclear plant must be based on local soil conditions, as well as on the seismicity, geology, and tectonics of the region. This report describes how such criteria can be developed by applying the latest technology associated with analytical predictions of site-dependent ground motions and with the use of composite spectra obtained from the current library of strong motion records. Recommended procedures for defining vibratory ground motion criteria contain the following steps: (1) geologic and seismologic studies; (2) site soils investigations; (3) site response sensitivity studies; (4) evaluation of local site response characteristics; (5) selection of site-matched records; and (6) appraisal and selection of seismic input criteria. An in-depth discussion of the engineering characteristics of earthquake ground motions including parameters used to characterize earthquakes and strong motion records, geologic factors that influence ground shaking, the current strong motion data base, and case histories of the effects of past earthquake events is presented. Next, geotechnical investigations of the seismologic, geologic, and site soil conditions required to develop vibratory motion criteria are briefly summarized. The current technology for establishing vibratory ground motion criteria at nuclear plant sites, including site-independent and site-dependent procedures that use data from strong motion records and from soil response analyses is described. (auth)

Siting nuclear power plants

International Nuclear Information System (INIS)

Yellin, J.; Joskow, P.L.

1980-01-01

The first edition of this journal is devoted to the policies and problems of siting nuclear power plants and the question of how far commercial reactors should be placed from urban areas. The article is divided into four major siting issues: policies, risk evaluation, accident consequences, and economic and physical constraints. One concern is how to treat currently operating reactors and those under construction that were established under less-stringent criteria if siting is to be used as a way to limit the consequences of accidents. Mehanical cost-benefit analyses are not as appropriate as the systematic use of empirical observations in assessing the values involved. Stricter siting rules are justified because (1) opposition because of safety is growing: (2) remote siting will make the industry more stable; (3) the conflict is eliminated between regulatory policies and the probability basis for nuclear insurance; and (4) joint ownership of utilities and power-pooling are increasing. 227 references, 7 tables

Review of underground siting of nuclear power plants

International Nuclear Information System (INIS)

1974-01-01

A review of the potential for the underground siting of nuclear power generating plants has been undertaken. The review comprised a survey and assessment of relevant published documents currently available, together with discussions with Government sponsored agencies and other bodies, to evaluate the current status of technology related to the design and construction of underground nuclear power plants. It includes a review of previous work related to the underground siting of power plants and other facilities; a preliminary evaluation of the relative merits of the various concepts of undergrounding which have been proposed or constructed; a review of current technology as it relates to the requirements for the design, construction and operation of underground nuclear power plants; an examination of the safety and environmental aspects; and the identification of areas of further study which will be required if the underground is to be established as a fully viable alternative to surface siting. No attempt has been made to draw final conclusions at this stage. Nothing has been found to suggest that the underground siting concept could not provide a viable alternative to the surface concept. It is also apparent that no major technological developments are required. It is not clear, however, whether the improvements in safety and containment postulated for the underground can be realized at an economic cost; or even whether any additional cost is in fact involved. The problem is essentially site dependent and requires further study for which recommendations are made. (auth)

Site and plant species are important determinants of the Methylobacterium community composition in the plant phyllosphere.

Science.gov (United States)

Knief, Claudia; Ramette, Alban; Frances, Lisa; Alonso-Blanco, Carlos; Vorholt, Julia A

2010-06-01

The plant phyllosphere constitutes a habitat for numerous microorganisms; among them are members of the genus Methylobacterium. Owing to the ubiquitous occurrence of methylobacteria on plant leaves, they represent a suitable target for studying plant colonization patterns. The influence of the factor site, host plant species, time and the presence of other phyllosphere bacteria on Methylobacterium community composition and population size were evaluated in this study. Leaf samples were collected from Arabidopsis thaliana or Medicago truncatula plants and from the surrounding plant species at several sites. The abundance of cultivable Methylobacterium clearly correlated with the abundance of other phyllosphere bacteria, suggesting that methylobacteria constitute a considerable and rather stable fraction of the phyllosphere microbiota under varying environmental conditions. Automated ribosomal intergenic spacer analysis (ARISA) was applied to characterize the Methylobacterium community composition and showed the presence of similar communities on A. thaliana plants at most sites in 2 consecutive years of sampling. A substantial part of the observed variation in the community composition was explained by site and plant species, especially in the case of the plants collected at the Arabidopsis sites (50%). The dominating ARISA peaks that were detected on A. thaliana plants were found on other plant species grown at the same site, whereas some different peaks were detected on A. thaliana plants from other sites. This indicates that site-specific factors had a stronger impact on the Methylobacterium community composition than did plant-specific factors and that the Methylobacterium-plant association is not highly host plant species specific.

Remote sensing for nuclear power plant siting

International Nuclear Information System (INIS)

Siegal, B.S.; Welby, C.W.

1981-01-01

It is shown that satellite remote sensing provides timely and cost-effective information for siting and site evaluation of nuclear power plants. Side-looking airborne radar (SLAR) imagery is especially valuable in regions of prolonged cloud cover and haze, and provides additional assurance in siting and licensing. In addition, a wide range of enhancement techniques should be employed and different types of image should be color-combined to provide structural and lithologic information. Coastal water circulation can also be studied through repetitive coverage and the inherently synoptic nature of imaging satellites. Among the issues discussed are snow cover, sun angle, and cloud cover, and actual site evaluation studies in the Bataan peninsula of the Philippines and Laguna Verde, California

An integrated approach to site selection for nuclear power plants

International Nuclear Information System (INIS)

Hassan, E.M.A.

1975-01-01

A method of analysing and evaluating the large number of factors influencing site selection is proposed, which can interrelate these factors and associated problems in an integrated way and at the same time establish a technique for site evaluation. The objective is to develop an integrated programme that illustrates the complexity and dynamic interrelationships of the various factors to develop an improved understanding of the functions and objectives of siting nuclear power plants and would aim finally at the development of an effective procedure and technique for site evaluation and/or comparative evaluation for making rational site-selection decisions. (author)

Safety in nuclear power plant siting. A code of practice

International Nuclear Information System (INIS)

1978-01-01

This publication is brought out within the framework of establishing Codes of Practice and Safety Guides for nuclear power plants: NUSS programme. The scope of the document encompasses site and site-plant interaction factors related to operational states and accident conditions. The purpose of the Code is to give criteria and procedures to be applied as appropriate to operational states and accident conditions, including those which could lead to emergency situations. This Code is mainly concerned with severe events of low probability which relate to the siting of nuclear power plants and have to be considered in designing a particular nuclear power plant. Annex: Examples of natural and man-made events relevant for design basis evaluation

Siting studies for new nuclear power plants in Argentina

International Nuclear Information System (INIS)

Barbaran, Gustavo A.

2008-01-01

This paper is a summary of the thesis prepared by the Group of Prospective and Energy Planning of the National Atomic Energy Commission for the 'Specialization on Applications of Nuclear Technology Course' of the Instituto Balseiro in 2007. It describes the evolution of siting studies through time and the main focus worldwide in this type of studies. Then, it makes a brief review of previous siting studies of nuclear power plants conducted in Argentina. It carries out a description of the methodology to conduct a site evaluation for nuclear power plants according to actual international criteria. Finally, it describes the licensing process that follows every site study. (author) [es

Risk-benefit evaluation of nuclear power plant siting

International Nuclear Information System (INIS)

Miettinen, J.; Savolainen, I.; Silvennoinen, P.

1976-01-01

An assessment scheme is described for the risk-benefit analyses of nuclear power versus conventional alternatives. Given the siting parameters for the proposed nuclear plant an economic comparison is made with the most advantageous competitive conventional production scenario. The economic benefit is determined from the differential discounted annual energy procurement cost as a function of the real interest rate and amortization time. The risk analysis encompasses the following factors: radiation risks in normal operation, reactor accident hazards and economic risks, atmospheric pollutants from the conventional power plants, and fuel transportation. The hazards are first considered in terms of probabilistic dose distributions. In the second stage risk components are converted to a compatible form where excess mortality is used as the risk indicator. Practical calculations are performed for the power production alternatives of Helsinki where district heat would be extracted from the nuclear power plant. At the real interest rate of 10% and amortization time of 20 yr the 1000 MW(e) nuclear option is found to be Pound9.1 m per yr more economic than the optimal conventional scenario. Simultaneously the nuclear alternative is estimated to reduce excess mortality by 2 to 5 fatal injuries annually. (author)

Dispersion of radioactive material in air and water and consideration of population distribution in site evaluation for nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2004-01-01

The IAEA issues Safety Requirements and Safety Guides pertaining to nuclear power plants and activities in the field of nuclear energy, on the basis of its Safety Fundamentals publication on The Safety of Nuclear Installations. The present Safety Guide, which supplements the Code on the Safety of Nuclear Power Plants: Siting, concerns the effects of a nuclear power plant on the surrounding region and the consideration of population distribution in the siting of a plant. This Safety Guide makes recommendations on how to meet the requirements of the Code on the Safety of Nuclear Power Plants: Siting, on the basis of knowledge of the mechanisms for the dispersion of effluents discharged into the atmosphere and into surface water and groundwater. Relevant site characteristics and safety considerations are discussed. Population distribution, the projected population growth rate, particular geographical features, the capabilities of local transport networks and communications networks, industry and agriculture in the region, and recreational and institutional activities in the region should be considered in assessing the feasibility of developing an emergency response plan. In the selection of a site for a facility using radioactive material, such as a nuclear power plant, account should be taken of any local features that might be affected by the facility and of the feasibility of off-site intervention, including emergency response and protective actions. This is in addition to the evaluation of any features of the site itself that might affect the safety of the facility. This Safety Guide recommends methods for the assessment of regional and local characteristics. This Safety Guide supersedes four earlier IAEA Safety Guides, namely: Atmospheric Dispersion in Nuclear Power Plant Siting (Safety Series No. 50-SG-S3 (1980)). Site Selection and Evaluation for Nuclear Power Plants with Respect to Population Distribution (Safety Series No. 50-SG-S4 (1980)). Hydrological

Dispersion of radioactive material in air and water and consideration of population distribution in site evaluation for nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2002-01-01

The IAEA issues Safety Requirements and Safety Guides pertaining to nuclear power plants and activities in the field of nuclear energy, on the basis of its Safety Fundamentals publication on The Safety of Nuclear Installations. The present Safety Guide, which supplements the Code on the Safety of Nuclear Power Plants: Siting, concerns the effects of a nuclear power plant on the surrounding region and the consideration of population distribution in the siting of a plant. This Safety Guide makes recommendations on how to meet the requirements of the Code on the Safety of Nuclear Power Plants: Siting, on the basis of knowledge of the mechanisms for the dispersion of effluents discharged into the atmosphere and into surface water and groundwater. Relevant site characteristics and safety considerations are discussed. Population distribution, the projected population growth rate, particular geographical features, the capabilities of local transport networks and communications networks, industry and agriculture in the region, and recreational and institutional activities in the region should be considered in assessing the feasibility of developing an emergency response plan. In the selection of a site for a facility using radioactive material, such as a nuclear power plant, account should be taken of any local features that might be affected by the facility and of the feasibility of off-site intervention, including emergency response and protective actions. This is in addition to the evaluation of any features of the site itself that might affect the safety of the facility. This Safety Guide recommends methods for the assessment of regional and local characteristics. This Safety Guide supersedes four earlier IAEA Safety Guides, namely: Atmospheric Dispersion in Nuclear Power Plant Siting (Safety Series No. 50-SG-S3 (1980)); Site Selection and Evaluation for Nuclear Power Plants with Respect to Population Distribution (Safety Series No. 50-SG-S4 (1980)); Hydrological

Chemistry evaluation in French EDF Nuclear Power Plants

International Nuclear Information System (INIS)

Jacquier, Hervé

2014-01-01

The Nuclear Production Division of EDF is comprised of 19 power stations (58 PWR reactors) and 2 national engineering organisations. Nuclear Inspection (IN) is an internal assessment unit of the EDF Nuclear Production Directorate. At the request of the Directorate, it carries out periodic evaluations of all the units of the division. The evaluation of the nuclear sites (EGE: Overall Excellence Assessment) is carried out every 4 years, an intermediate evaluation is also carried out between each EGE. These evaluations are independent of the WANO and IAEA evaluations. Exchanges are carried out between Nuclear Inspection and the other international operators (for example, USA (INPO), England, China...) to share site evaluation methods. These evaluations are carried out by a team of 30 inspectors, reinforced during each evaluation by 10 peers who come from the various French nuclear sites. Nuclear Inspection produces a performance standards document for each FUNCTIONAL AREA, which is based on the requirements of the company. On the whole, 13 areas are evaluated during each inspection, in particular: Management, Operations, Maintenance, Engineering and Chemistry. The area of reactor plant chemistry has been evaluated since 2009. The Chemistry performance standards document is written from the EDF internal requirements and international references. During site evaluations, all the performance standards are assessed for compliance. The Chemistry performance standards document is comprised of 3 topics: Management of plant chemistry, The respect of the chemical and radiochemical specifications, The condition of the laboratories and the sampling lines, measuring equipment, and chemical products. The evaluations carried out make it possible to define strengths and weaknesses which the sites must address. After each evaluation, the assessment is presented to the site management and to the director of EDF Nuclear Production. For 4 years these evaluations have allowed progress to

Evaluation of utility monitoring and preoperational hydrothermal modeling at three nuclear power plant sites

International Nuclear Information System (INIS)

Marmer, G.J.; Policastro, A.J.

1977-01-01

This paper evaluates the preoperational hydrothermal modeling and operational monitoring carried out by utilities as three nuclear-power-plant sites using once-through cooling. Our work was part of a larger study to assess the environmental impact of operating plants for the Nuclear Regulatory Commission (NRC) and the suitability of the NRC Environmental Technical Specifications (Tech Specs) as set up for these plants. The study revealed that the plume mappings at the Kewaunee, Zion, and Quad Cities sites were generally satisfactory in terms of delineating plume size and other characteristics. Unfortunately, monitoring was not carried out during the most critical periods when largest plume size would be expected. At Kewaunee and Zion, preoperational predictions using analytical models were found to be rather poor. At Kewaunee (surface discharge), the Pritchard Model underestimated plume size in the near field, but grossly overestimated the plume's far-field extent. Moreover, lake-level variations affected plume dispersion, yet were not considered in preoperational predictions. At Zion (submerged discharge) the Pritchard Model was successful only in special, simple cases (single-unit operation, no stratification, no reversing currents, no recirculation). Due to neglect of the above-mentioned phenomena, the model underpredicted plume size. At Quad Cities (submerged discharge), the undistorted laboratory model predicted plume dispersion for low river flows. These low flow predictions appear to be reasonable extrapolations of the field data acquired at higher flows

Site selection and evaluation studies of the Waste Isolation Pilot Plant (WIPP), Los Medanos, Eddy County, NM

International Nuclear Information System (INIS)

Griswold, G.B.

1977-12-01

Bedded-salt deposits of the Salado Formation have been selected for evaluation for a proposed Waste Isolation Pilot Plant (WIPP) to be located in Eddy County, NM, approximately 26 mi east of Carlsbad. Site selection and evaluation studies that included geologic mapping, geophysical surveys, drilling, and resource appraisal were conducted over and under the prospective location. The lower portion of the Salado meets essential criteria for waste isolation. Beds chosen for waste storage lie 2074 to 2730 ft below the surface. High-purity salt exists at these depths, and the geologic structure revealed by geophysical surveys indicates that these beds are essentially flat. Additional geophysical surveys are now under way. The initial interpretation of the new data indicates that more structure may exist in the salt beds in the northern portion of the site area. Full evaluation of potentially commercial deposits of potash and natural gas within the WIPP site will be reported by separate studies, as will be the hydrologic details of the region

Site evaluation for nuclear installations. Safety requirements

International Nuclear Information System (INIS)

2003-01-01

This Safety Requirements publication supersedes the Code on the Safety of Nuclear Power Plants: Siting, which was issued in 1988 as Safety Series No. 50-C-S (Rev. 1). It takes account of developments relating to site evaluations for nuclear installations since the Code on Siting was last revised. These developments include the issuing of the Safety Fundamentals publication on The Safety of Nuclear Installations, and the revision of various safety standards and other publications relating to safety. Requirements for site evaluation are intended to ensure adequate protection of site personnel, the public and the environment from the effects of ionizing radiation arising from nuclear installations. It is recognized that there are steady advances in technology and scientific knowledge, in nuclear safety and in what is considered adequate protection. Safety requirements change with these advances and this publication reflects the present consensus among States. This Safety Requirements publication was prepared under the IAEA programme on safety standards for nuclear installations. It establishes requirements and provides criteria for ensuring safety in site evaluation for nuclear installations. The Safety Guides on site evaluation listed in the references provide recommendations on how to meet the requirements established in this Safety Requirements publication. The objective of this publication is to establish the requirements for the elements of a site evaluation for a nuclear installation so as to characterize fully the site specific conditions pertinent to the safety of a nuclear installation. The purpose is to establish requirements for criteria, to be applied as appropriate to site and site-installation interaction in operational states and accident conditions, including those that could lead to emergency measures for: (a) Defining the extent of information on a proposed site to be presented by the applicant; (b) Evaluating a proposed site to ensure that the site

Projecting labor demand and worker immigration at nuclear power plant construction sites: an evaluation of methodology

International Nuclear Information System (INIS)

Herzog, H.W. Jr; Schlottmann, A.M.; Schriver, W.R.

1981-12-01

The study evaluates methodology employed for the projection of labor demand at, and worker migration to, nuclear power plant construction sites. In addition, suggestions are offered as to how this projection methodology might be improved. The study focuses on projection methodologies which forecast either construction worker migration or labor requirements of alternative types of construction activity. Suggested methodological improvements relate both to institutional factors within the nuclear power plant construction industry, and to a better use of craft-specific data on construction worker demand/supply. In addition, the timeliness and availability of the regional occupational data required to support, or implement these suggestions are examined

Quaternary ground siting technology of nuclear power plants

International Nuclear Information System (INIS)

Nishi, K.; Kokusho, T.; Iwatate, Y.; Ishida, K.; Honsho, S.; Okamoto, T.; Tohma, J.; Tanaka, Y.; Kanatani, M.

1992-01-01

A seismic stability evaluation method for a nuclear power plant to be located on Quaternary sandy/gravelly ground is discussed herein in terms of a geological and geotechnical survey, a design earthquake motion evaluation and geotechnical seismic stability analyses. The geological and geotechnical exploration tunnel in the rock foundation siting will be difficult in the Quaternary ground siting. Boring, geophysical surveys and soil sampling will play a major role in this case. A design earthquake input spectrum for this siting is proposed to take in account the significant effect of longer period motion on ground stability. Equivalent and non-linear analyses demonstrate the seismic stability of the foundation ground so long as the soil density is high. (author)

Power plant site evaluation - Douglas Point site. Volume 1, part 2. Final report

International Nuclear Information System (INIS)

1977-11-01

This is part of a series of reports containing an evaluation of the proposed Douglas Point nuclear generating station site located on the Potomac River in Maryland 30 miles south of Washington, DC. This report contains sections on cooling tower air emissions, noise impacts, transmission line effects, radiation from normal releases, site features affecting radiological accidents, and meteorology

Site evaluation for the Waste Isolation Pilot Plant (WIPP)

International Nuclear Information System (INIS)

Hill, L.R.

1979-01-01

Preliminary site selection activities for the WIPP are complete now; these consisted primarily of national and regional studies over the past fifteen years, and resulted in selection of the WIPP study area for geological characterization. The work of geological characterization should be considered to have begun with the drilling of ERDA 9 at the center of the WIPP study area and the initiation of seismic reflection work on the site. That geological characterization, which is primarily oriented to provide specific data concerning the present geology of the site, was virtually complete in December, 1978, when the Geological Characterization Report was submitted to the Department of Energy; much basic information has been gathered indicating no major technical problems with the site as it is now understood. Studies of long-term processes which might affect a repository or have an effect on safety analyses will now be the major geotechnical activity for the WIPP site evaluation team, some of these activities are already underway. These studies will deal with the age of significant features and the rates and processes which produce those features. The information so gained will be useful in increasing the confidence in evaluation of the safety of a repository

Environmental site description for a Uranium Atomic Vapor Laser Isotope Separation (U-AVLIS) production plant at the Portsmouth Gaseous Diffusion Plant site

International Nuclear Information System (INIS)

Marmer, G.J.; Dunn, C.P.; Filley, T.H.; Moeller, K.L.; Pfingston, J.M.; Policastro, A.J.; Cleland, J.H.

1991-09-01

Uranium enrichment in the United States has utilized a diffusion process to preferentially enrich the U-235 isotope in the uranium product. In the 1970s, the US Department of Energy (DOE) began investigating more efficient and cost-effective enrichment technologies. In January 1990, the Secretary of Energy approved a plan for the demonstration and deployment of the Uranium Atomic Vapor Laser isotope Separation (U-AVLIS) technology with the near-term goal to provide the necessary information to make a deployment decision by November 1992. Initial facility operation is anticipated for 1999. A programmatic document for use in screening DOE sites to locate a U-AVLIS production plant was developed and implemented in two parts. The first part consisted of a series of screening analyses, based on exclusionary and other criteria, that identified a reasonable number of candidate sites. The final evaluation, which included sensitivity studies, identified the Oak Ridge Gaseous Diffusion Plant (ORGDP) site, the Paducah Gaseous Diffusion Plant (PGDP) site, and the Portsmouth Gaseous Diffusion Plant (PORTS) site as having significant advantages over the other sites considered. This environmental site description (ESD) provides a detailed description of the PORTS site and vicinity suitable for use in an environmental impact statement (EIS). This report is based on existing literature, data collected at the site, and information collected by Argonne National Laboratory (ANL) staff during site visits. The organization of the ESD is as follows. Topics addressed in Sec. 2 include a general site description and the disciplines of geology, water resources, biotic resources, air resources, noise, cultural resources, land use. Socioeconomics, and waste management. Identification of any additional data that would be required for an EIS is presented in Sec. 3

Environmental site description for a Uranium Atomic Vapor Laser Isotope Separation (U-AVLIS) production plant at the Portsmouth Gaseous Diffusion Plant site

Energy Technology Data Exchange (ETDEWEB)

Marmer, G.J.; Dunn, C.P.; Filley, T.H.; Moeller, K.L.; Pfingston, J.M.; Policastro, A.J.; Cleland, J.H.

1991-09-01

Uranium enrichment in the United States has utilized a diffusion process to preferentially enrich the U-235 isotope in the uranium product. In the 1970s, the US Department of Energy (DOE) began investigating more efficient and cost-effective enrichment technologies. In January 1990, the Secretary of Energy approved a plan for the demonstration and deployment of the Uranium Atomic Vapor Laser isotope Separation (U-AVLIS) technology with the near-term goal to provide the necessary information to make a deployment decision by November 1992. Initial facility operation is anticipated for 1999. A programmatic document for use in screening DOE sites to locate a U-AVLIS production plant was developed and implemented in two parts. The first part consisted of a series of screening analyses, based on exclusionary and other criteria, that identified a reasonable number of candidate sites. The final evaluation, which included sensitivity studies, identified the Oak Ridge Gaseous Diffusion Plant (ORGDP) site, the Paducah Gaseous Diffusion Plant (PGDP) site, and the Portsmouth Gaseous Diffusion Plant (PORTS) site as having significant advantages over the other sites considered. This environmental site description (ESD) provides a detailed description of the PORTS site and vicinity suitable for use in an environmental impact statement (EIS). This report is based on existing literature, data collected at the site, and information collected by Argonne National Laboratory (ANL) staff during site visits. The organization of the ESD is as follows. Topics addressed in Sec. 2 include a general site description and the disciplines of geology, water resources, biotic resources, air resources, noise, cultural resources, land use. Socioeconomics, and waste management. Identification of any additional data that would be required for an EIS is presented in Sec. 3.

Seismic stability evaluation using 2-D FEM analysis for modeling nuclear power plants sited on gravel soil

International Nuclear Information System (INIS)

Iba, T.; Konno, T.; Irino, K.; Hama, I.; Oguro, E.; Iizuka, S.; Enami, A.

1995-01-01

Throughout Europe and the United States, many nuclear power plants have been built on Quaternary deposit sites. While in Japan, all nuclear power plants have been built at rock sites primarily to maintain a high seismic resistivity. However, as more nuclear power plants are planned for the future, it has become necessary to develop new siting technology from the stand point of expanding the available range of site selection and effective utilization of land. A draft on guidelines of the seismic design for siting on Quaternary deposits is being carried out with a purpose to ensure proper design and construction for such sites. (author). 10 figs., 2 tabs

Siting and early-stage project management of nuclear power plant

International Nuclear Information System (INIS)

Wang Kai; Li Guojin

2013-01-01

In this paper, difficulties and challenges facing in siting of nuclear power plant after Fukushima nuclear accident is introduced. The key points for siting are analyzed. The site characteristics related to nuclear safety and the evaluated methods are discussed. From project management perspective, main procedures and key points for the early-stage of a nuclear power project are described. (authors)

American National Standard: guidelines for evaluating site-related geotechnical parameters at nuclear power sites

International Nuclear Information System (INIS)

Anon.

1978-01-01

This standard presents guidelines for evaluating site-related geotechnical parameters for nuclear power sites. Aspects considered include geology, ground water, foundation engineering, and earthwork engineering. These guidelines identify the basic geotechnical parameters to be considered in site evaluation, and in the design, construction, and performance of foundations and earthwork aspects for nuclear power plants. Also included are tabulations of typical field and laboratory investigative methods useful in identifying geotechnical parameters. Those areas where interrelationships with other standards may exist are indicated

Evaluation of population density and distribution criteria in nuclear power plant siting

International Nuclear Information System (INIS)

Young, M.

1994-06-01

The NRC has proposed revisions to 10 CFR 100 which include the codification of nuclear reactor site population density limits to 500 people per square mile, at the siting stage, averaged over any radial distance out to 30 miles, and 1,000 people per square mile within the 40-year lifetime of a nuclear plant. This study examined whether there are less restrictive alternative population density and/or distribution criteria which would provide equivalent or better protection to human health in the unlikely event of a nuclear accident. This study did not attempt to directly address the issue of actual population density limits because there are no US risk standards established for the evaluation of population density limits. Calculations were performed using source terms for both a current generation light water reactor (LWR) and an advanced light water reactor (ALWR) design. The results of this study suggest that measures which address the distribution of the population density, including emergency response conditions, could result in lower average individual risks to the public than the proposed guidelines that require controlling average population density. Studies also indicate that an exclusion zone size, determined by emergency response conditions and reactor design (power level and safety features), would better serve to protect public health than a rigid standard applied to all sites

Regional siting survey for thermal power plants in the state of Ohio

International Nuclear Information System (INIS)

Elkins, M.L.; DiNunno, J.J.

1975-01-01

The selection and evaluation of sites for power plants have become increasingly difficult in recent years as pressures from various societal segments have resulted in government restraints on selection and burning of fossil fuels, on methods of heat dissipation, on acquisition of transmission line rights-of-way, and on environmental impact in general. The key elements in successful application of power plant siting technology are the development of the proper balance among the basic siting considerations and the understanding that level of detail in a study varies in an inverse relationship with the siting area under examination. As the first step in the process of selection and eventual licensing of new thermal power plant sites for a utility in the State of Ohio, the entire state was screened to determine promising candidate regions large enough to offer several possible candidate sites for thermal power plants. Because of the size of the area under consideration and the advantages of developing sites with an ultimate capacity for more than one power plant, sites with an installed capacity of 1100 to 4400 MW(e) were considered for this study. As a result of the preliminary screening conducted in four distinct steps, three candidate regions showed the best overall promise for either nuclear or fossil-fueled power plant development. Tentative identification was made of candidate sites within these candidate regions, and follow-on studies conducted in an increasing level of detail are presently in progress to determine the candidate site(s) most promising for power plant siting. (U.S.)

Nuclear power plant site selection: a case study

International Nuclear Information System (INIS)

Lugasi, Y.; Mehrez, A.; Sinuany-Stern, Z.

1985-01-01

Selecting the site for a nuclear power plant involves the evaluation of numerous criteria and the professional judgment of various experts. The Israel Atomic Energy Commission has been concerned with the problem of selecting a site for a nuclear power station. Previous studies have been performed by the commission to identify potential sites. There were initial screenings where potential sites were chosen according to various minimal criteria and international standards. Only sites that met all the criteria were chosen. A study was made to find the most preferred site among the potential sites that met all the criteria. Two mathematical approaches were used: Keeney's multiattribute utility function and Saaty's eigenvalue prioritization technique. Both models ranked the same site as the most desirable; however, the models differed in their ranking of the other sites

Site survey for nuclear power plants

International Nuclear Information System (INIS)

1984-01-01

This Safety Guide describes the first stage of the siting process for nuclear power plants - the site survey to select one or more preferred candidate sites. Its purpose is to recommend procedures and provide information for use in implementing a part of the Code of Practice on Safety in Nuclear Power Plant Siting (IAEA Safety Series No.50-C-S). The organization, procedures, methodologies, guidance for documenting the site survey process and examples of detailed procedures on some safety-related site characteristics are given in the Guide

Evaluation of water quality parameters and associated environmental impact at nuclear power plant sites

International Nuclear Information System (INIS)

Joshi, M.L.; Hegde, A.G.

2005-01-01

The Nuclear Power Plants use a large quantity of water for the purpose of cooling the turbine condenser. The heated effluents are discharged to aquatic environment by means of once through cooling wherever large water bodies like seacoast or fresh water reservoir are available. The quality of water bodies are important for the growth and biodiversity of aquatic organisms. Several environmental factors like Temperature pH, Dissolved Oxygen have a bearing on the life cycle of aquatic organisms. The paper describes the evaluation of water quality parameters at the two typical sites one on the sea coast (Tarapur) and other at inland site Kaiga and discusses the environmental impact due to discharge to aquatic environment. It is found that the environmental impacts due to both heated effluents and radioactivity are insignificant. The water quality parameters are found to be well within the prescribed standards. (author)

Geomorphologic specificities of selected sites for nuclear power plants in Czechoslovakia

International Nuclear Information System (INIS)

Kalvoda, J.; Demek, J.

1991-01-01

The contribution of geomorphology to the complex evaluation of properties of sites for the construction and operation of nuclear facilities is demonstrated. The unique manifestation of the present geodynamics at the Jaslovske Bohunice nuclear power plant locality and the spatial correlations of annals of the specific morphotectonic development of georeliefs of that nuclear power plant with the location of the epicentral earthquake zones are shown. The results of the geomorphological survey in the surroundings of the Temelin nuclear power plant construction site are described and a drawing is reproduced showing how the georelief of this locality divides into areas with different categories of occurrence of morpho-structural formations. For the Tetov locality, where the construction of a nuclear power plant is planned, the changes in the course of the Labe (Elbe) river which occurred in the Pleistocene are of importance in the assessment of the intensity of geodynamic processes. The geomorphological and geotectonic complexity of the planned Blahutovice nuclear power plant construction site is demonstrated. A drawing shows the morphotectonic situation in the surroundings of that construction site. (Z.S.). 4 figs

Regional approaches to power plant siting in the United States of America

International Nuclear Information System (INIS)

DiNunno, J.J.

1975-01-01

The selection and evaluation of sites for power plants in the United States of America have become increasingly difficult in recent years as pressures from various societal segments have resulted in governmental restraints on selection and burning of fossil fuels, methods of heat dissipation, acquisition of transmission rights of way, and on environmental impact of industrialization in general. New legislation at both Federal and state levels has been enacted that influences power plant siting. In addition to environmental requirements that must be satisfied, implementing procedures require documented justification for sites chosen and public disclosure of the basis for selection. Some states have consolidated their regulatory activities in the power plant siting area to provide for a more unified approach to these problems. Although nuclear plants have by far the most rigorous requirements for documentation of site selection and plant design, the application of the same general philosophies to fossil plants has been made in several states and can be anticipated elsewhere. Individual site-related investigations have not so much changed in basics as they have been enlarged in scope. Whereas in the past the search for siting alternatives was frequently confined to a utility's service area, the additional siting constraints represented in environmental laws, the economies of size of nuclear power plants, and the sharing of plant capacities among utilities have contributed to a widening of the search area. Several states have assumed the responsibility for site search and investigation and their efforts extend state-wide. This paper discusses applications of regional approaches to power plant siting in the United States of America using case studies made by NUS Corporation, an engineering/environmental consulting firm. The universality of these approaches is indicated, leaving to national policies and goals the importance of values assigned to the basic siting factors

Collection and evaluation of complete and partial losses of off-site power at nuclear power plants

International Nuclear Information System (INIS)

Battle, R.E.

1985-02-01

Events involving loss of off-site power that have occurred at nuclear power plants through 1983 are described and categorized as complete or partial losses. The events were identified as plant-centered or grid-related failures. In addition, the causes of the failures were classified as weather, human error, design error, or hardware failure. The plant-centered failures were usually of shorter duration than the weather-related grid failures. For this reason, the weather-related events were reviewed in detail. Design features that may be important factors affecting off-site power system reliability were tabulated for most of the operating nuclear power plants. The tabulated information was provided to NRC for a statistical analysis to determine the importance of these design features for losses of off-site power. The frequency of losses of off-site power versus duration was estimated for three time periods. The frequency of loss of off-site power was estimated to be 0.09/reactor-year based on industry-wide data for the years 1959 through 1983

Site and feasibility studies of a first nuclear power plant in Morocco

International Nuclear Information System (INIS)

Righi, M.

1988-11-01

Basing on the estimated studies related to the evaluation of future needs of electrical energy, the launching of a nuclear power program in Morocco is confirmed necessary. A complete study of sites and feasibility has been carried out. Taking into account the site selection factors two sites: BIR ELHAR and SIDI BOULBRA have been kept as candidate sites. The evaluation of seismic and geotechnical risks of the power plant impact on the environment and risks related to human activities has led to privilege the SIDI BOULBRA site. The studies for confirming this site are summarized. 4 figs. (F.M.)

Selected bibliography for the extraction of uranium from seawater: evaluation of uranium resources and plant siting

Energy Technology Data Exchange (ETDEWEB)

Chen, A.C.T.; Gordon, L.I.; Rodman, M.R.; Binney, S.E.

1979-02-06

This bibliography contains 471 references pertaining to the evaluation of U.S. territorial ocean waters as a potential uranium resource and to the selection of a site for a plant designed for the large scale extraction of uranium from seawater. This bibliography was prepared using machine literature retrieval, bibliographic, and work processing systems at Oregon State University. The literature cited is listed by author with indices to the author's countries, geographic areas of study, and to a set of keywords to the subject matter.

Selected bibliography for the extraction of uranium from seawater: evaluation of uranium resources and plant siting

International Nuclear Information System (INIS)

Chen, A.C.T.; Gordon, L.I.; Rodman, M.R.; Binney, S.E.

1979-01-01

This bibliography contains 471 references pertaining to the evaluation of U.S. territorial ocean waters as a potential uranium resource and to the selection of a site for a plant designed for the large scale extraction of uranium from seawater. This bibliography was prepared using machine literature retrieval, bibliographic, and work processing systems at Oregon State University. The literature cited is listed by author with indices to the author's countries, geographic areas of study, and to a set of keywords to the subject matter

Recommended criteria for the evaluation of on-site nuclear power plant emergency plans, volume II: criteria

International Nuclear Information System (INIS)

1997-01-01

A critical review of existing Canadian and international nuclear power plant (NPP) emergency plans, evaluation criteria, and approaches has been conducted to provide AECB staff with information which can be used to assess the adequacy of NPP on-site emergency response plans. The results of this work are published in two volumes. Volume I, Basis Document, provides the reasons why certain requirements are in place. It also gives comprehensive references to various standards.Volume II, Criteria, contains the criteria which relate to on-site actions and their integration with control room activities and the roles of off-site responsible organizations. The recommended criteria provide information on what is required, and not on how to accomplish the requirements. The licensees are given the latitude to decide on the methods and processes needed to meet the requirements. The documents do not address NPP off-site plans and response capability, or the control room emergency operating procedures and response capability. This report contains only Volume II: Criteria. 55 refs., 2 tabs., 1 fig

Standard protocol for evaluation of environmental transfer factors around NPP sites

International Nuclear Information System (INIS)

Hegde, A.G.; Verma, P.C.; Rao, D.D.

2009-01-01

This document presents the standard procedures for evaluation of site specific environmental transfer factors around NPP sites. The scope of this document is to provide standard protocol to be followed for evaluation of environmental transfer factors around NPP sites. The studies on transfer factors are being carried out at various NPP sites under DAE-BRNS projects for evaluation of site specific transfer factors for radionuclides released from power plants. This document contains a common methodology in terms of sampling, processing, measurements and analysis of elemental/radionuclides, while keeping the site specific requirements also in place. (author)

In situ bioremediation (natural attenuation) at a gas plant waste site

International Nuclear Information System (INIS)

Ginn, J.S.; Sims, R.C.

1995-01-01

A former manufactured gas plant (MGP) waste site in New York was evaluated with regard to natural attenuation of polycyclic aromatic hydrocarbons (PAHs). Parent-compound concentrations of PAHs within an aquifer plume were observed to decrease with time subsequent to source removal of coal tar. Biotransformation-potential studies indicated that indigenous microorganisms in soil from the site were capable of degrading naphthalene and phenanthrene. A biochemical metabolite of phenanthrene degradation, 1-hydroxy-2-naphthoic acid (1H2NA), was tentatively characterized in coal-tar-contaminated soil from the site-based on liquid chromatographic retention time. Kinetic information was developed for the disappearance of phenanthrene and 1H2NA in nonspiked contaminated soil at the site. The Microtox trademark bioassay was used to evaluate toxicity trends in contaminated soil at the site. Results from the Microtox trademark indicated a decreasing trend in toxicity with respect to time in contaminated site soil. Research results were evaluated with regard to the National Research Council's guidelines for evaluating in situ bioremediation, and were used to enhance site characterization and monitoring information for evaluating the role of bioremediation as part of natural attenuation of PAHs at coal-tar-contaminated sites

Technology overview: assessment of social values in thermal power plant siting, social impact methodology evaluation

International Nuclear Information System (INIS)

Anon.

1978-01-01

A methodology was developed to facilitate the selection of favorable thermal power plant site and design alternatives from the community perspective. A two-stage, multicriteria decision technique was employed to combine technical assessments of effects of the proposed site/design alternatives with corresponding community values. In the first stage, submodels are used to develop indices of plant impact on each of ten decision criteria. These criteria include effects on aesthetics, water quality, cost of power, air quality, ecology, social quality, local economy, recreational opportunities, cultural resources, and human health and safety. In the second stage, each of the impact indices is weighted by corresponding community values and then summed to provide an overall index of plant acceptability

Vascular Plants of the Hanford Site

Energy Technology Data Exchange (ETDEWEB)

Sackschewsky, Michael R.; Downs, Janelle L.

2001-09-28

This report provides an updated listing of the vascular plants present on and near the U.S. Department of Energy Hanford Site. This document is an update of a listing of plants prepared by Sackschewdky et al. in 1992. Since that time there has been a significant increase in the botanical knowledge of the Hanford Site. The present listing is based on an examination of herbarium collections held at PNNL, at WSU-Tri Cities, WSU-Pullman, Bringham Young University, and The University of Washington, and on examination of ecological literature derived from the Hanford and Benton county areas over the last 100 years. Based on the most recent analysis, there are approximately 725 different plant species that have been documented on or around the Hanford Site. This represents an approximate 20% increase in the number of species reported within Sackschewsky et al. (1992). This listing directly supports DOE and contractor efforts to assess the potential impacts of Hanford Site operations on the biological environment, including impacts to rare habitats and to species listed as endangered or\\ threatened. This document includes a listing of plants currently listed as endangered, threatened, or otherwise of concern to the Washington Natural Heritage Program or the U.S. Fish and Wildlife Service, as well as those that are currently listed as noxious weeds by the State of Washington. Also provided is an overview of how plants on the Hanford Site can be used by people. This information may be useful in developing risk assessment models, and as supporting information for clean-up level and remediation decisions.

Vascular Plants of the Hanford Site

International Nuclear Information System (INIS)

Sackschewsky, Michael R.; Downs, Janelle L.

2001-01-01

This report provides an updated listing of the vascular plants present on and near the U.S. Department of Energy Hanford Site. This document is an update of a listing of plants prepared by Sackschewdky et al. in 1992. Since that time there has been a significant increase in the botanical knowledge of the Hanford Site. The present listing is based on an examination of herbarium collections held at PNNL, at WSU-Tri Cities, WSU-Pullman, Brigham Young University, and The University of Washington, and on examination of ecological literature derived from the Hanford and Benton county areas over the last 100 years. Based on the most recent analysis, there are approximately 725 different plant species that have been documented on or around the Hanford Site. This represents an approximate 20% increase in the number of species reported within Sackschewsky et al. (1992). This listing directly supports DOE and contractor efforts to assess the potential impacts of Hanford Site operations

Evaluation of seismic hazards for nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2002-01-01

The main objective of this Safety Guide is to provide recommendations on how to determine the ground motion hazards for a plant at a particular site and the potential for surface faulting, which could affect the feasibility of construction and safe operation of a plant at that site. The guidelines and procedures presented in this Safety Guide can appropriately be used in evaluations of site suitability and seismic hazards for nuclear power plants in any seismotectonic environment. The probabilistic seismic hazard analysis recommended in this Safety Guide also addresses the needs for seismic hazard analysis of external event PSAs conducted for nuclear power plants. Many of the methods and processes described may also be applicable to nuclear facilities other than power plants. Other phenomena of permanent ground displacement (liquefaction, slope instability, subsidence and collapse) as well as the topic of seismically induced flooding are treated in Safety Guides relating to foundation safety and coastal flooding. Recommendations of a general nature are given in Section 2. Section 3 discusses the acquisition of a database containing the information needed to evaluate and address all hazards associated with earthquakes. Section 4 covers the use of this database for construction of a seismotectonic model. Sections 5 and 6 review ground motion hazards and evaluations of the potential for surface faulting, respectively. Section 7 addresses quality assurance in the evaluation of seismic hazards for nuclear power plants

Underground siting of nuclear power plants

International Nuclear Information System (INIS)

Pinto, S.; Telleschi, P.

1978-10-01

Two of the main underground siting alternatives, the rock cavity plant and the pit siting, have been investigated in detail and two layouts, developed for specific sites, have been proposed. The influence of this type of siting on normal operating conditions and during abnormal occurences have been investigated. (Auth.)

Evaluation of nuclear power plant siting by probabilistic assessment of environmental impacts

International Nuclear Information System (INIS)

Vuori, S.

1978-01-01

The work consists of the description of a probabilistic consequence assessment model ARANO, and the individual calculation schemes therein included. This assessment model has been applied to the risk/benefit and cost/benefit analyses of the siting of nuclear power plants. In addition, there have been made some comparisons with the alternative fossil fuelled energy production scenarios. (author)

Synthesis gas demonstration plant program, Phase I. Site confirmation report

Energy Technology Data Exchange (ETDEWEB)

1978-12-01

With few reservations, the Baskett, Kentucky site exhibits the necessary characteristics to suggest compatibility with the proposed Synthesis Gas Demonstration Plant Project. An evaluation of a broad range of technical disciplinary criteria in consideration of presently available information indicated generally favorable conditions or, at least, conditions which could be feasibly accommodated in project design. The proximity of the Baskett site to market areas and sources of raw materials as well as a variety of transportation facilities suggests an overall favorable impact on Project economic feasibility. Two aspects of environmental engineering, however, have been identified as areas where the completion or continuation of current studies are required before removing all conditions on site suitability. The first aspect involves the current contradictory status of existing land use and planning ordinances in the site area. Additional investigation of the legality of, and local attitudes toward, these present plans is warranted. Secondly, terrestrial and aquatic surveys of plant and animal life species in the site area must be completed on a seasonal basis to confirm the preliminary conclusion that no exclusionary conditions exist.

Nuclear power plant siting

International Nuclear Information System (INIS)

Sulkiewicz, M.; Navratil, J.

The construction of a nuclear power plant is conditioned on territorial requirements and is accompanied by the disturbance of the environment, land occupation, population migration, the emission of radioactive wastes, thermal pollution, etc. On the other hand, a nuclear power plant makes possible the introduction of district heating and increases the economic and civilization activity of the population. Due to the construction of a nuclear power plant the set limits of negative impacts must not be exceeded. The locality should be selected such as to reduce the unfavourable effects of the plant and to fully use its benefits. The decision on the siting of the nuclear power plant is preceded by the processing of a number of surveys and a wide range of documentation to which the given criteria are strictly applied. (B.H.)

External main-induced events in relation to nuclear power plant siting

International Nuclear Information System (INIS)

1981-01-01

This safety Guide recomments procedures and provides information for use in implementing that part of the code of safety in Nuclear Power Plant Siting (IAEA Safety Series No. 50-C-S) which concerns man-induced events external to the plant, up to the evaluation of corresponding design basis parameters. Like the code, the Guide forms part of the IAEA's programme, referred to as the NUSS programme, for establishing codes of practice and safety Guides relating to land-based stationary thermal neutron power plants

Study on Quaternary ground siting of nuclear power plant, (1)

International Nuclear Information System (INIS)

Kokusho, Takaji; Nishi, Koichi; Honsho, Shizumitsu

1991-01-01

A seismic stability evaluation method for a nuclear power plant to be located on a Quaternary sandy/gravelly ground is discussed herein in terms of the geological and geotechnical survey, design earthquake motion evaluation and geotechnical seismic stability analyses. The geological and geotechnical exploration tunnel in the rock-foundation siting will be difficult in the Quaternary ground siting. Boring, geophysical surveys and soil samplings will play a major role in this case. The design earthquake input spectrum for this siting is proposed so as to take account the significant effect of longer period motion on the ground stability. Equivalent and non-linear analyses demonstrate the seismic stability of the foundation ground so long as the soil density is high. (author)

Evaluation of Radiological Impacts on the Operating Kartini Reactor and Natural Radioactivity of the Site Plan of Nuclear Power Plant Area

International Nuclear Information System (INIS)

Yazid, M; Sutresna, G; Sulistyono, A; Ngasifudin

1996-01-01

This radiological impacts evaluation covered of radioactivity in water, soil, grass, air samples and ambient gamma radiation that have been carried out in the Kartini reactor area and in the site plan of nuclear power plan are at Ujung Lemah Abang, Jepara, Central Java. The aim of this research was to determine that radiological impacts in the environment around the Kartini reactor compared to natural radioactivity for site plan of nuclear power plan area. The radioactivity in the water, soil and grass samples ware measured by low background beta counting system and were identified by low background gamma spectrometer. The radioactivity in the air samples was measured by beta portable counting system and the ambient gamma radiation was measured by portable high pressurized ionization chamber model RSS-112 Reuther-Stokes. The reactor data measurement was compared to the site plan of nuclear power plant area data for evaluation of radiological impacts on the operating reactor. From the evaluation and comparison can be concluded there are no indication of the radionuclide release from the reactor operation. The average radiactivity in the water, soil grass and air sample from the reactor area were between 0.17 - 0.61 Bq/1; 0,47 - 0,74 Bq/g; 4.43 - 4.60 Bq/g.ash and 49.53 - 70.90 x 10 Bq/cc. The average radioactivity of those sample from the nuclear power plant area were between 0.06-0.90 Bq/I; 0.02-0.86 Bq/g; 1.68-8.07 Bq/g.ash and 65.0-152.3 x 10 Bq/cc. The ambient gamma radiation were between 6.9-36.7 urad/h for the reactor area and 6.8-19.2 urad/h for the nuclear power plant area

Use of plant and earthworm bioassays to evaluate remediation of soil from a site contaminated with polychlorinated biphenyls

Energy Technology Data Exchange (ETDEWEB)

Meier, J.R.; Chang, L.W.; Meckes, M.C.; Smith, M.K. [Environmental Protection Agency, Cincinnati, OH (United States); Jacobs, S. [DynCorp, Cincinnati, OH (United States); Torsella, J. [Oak Ridge Inst. of Science and Education, Cincinnati, OH (United States)

1997-05-01

Soil from a site heavily contaminated with polychlorinated biphenyls (PCBs) was treated with a pilot-scale, solvent extraction technology. Bioassays in earthworms and plants were used to examine the efficacy of the remediation process for reducing the toxicity of the soil. The earthworm toxicity bioassays were the 14-d survival test and 21-d reproduction test, using Lumbricus terrestris and Eisenia fetida andrei. The plant bioassays included phytotoxicity tests for seed germination and root elongation in lettuce and oats, and a genotoxicity test (anaphase aberrations) in Allium cepa (common onion). Although the PCB content of the soil was reduced by 99% (below the remediation goal), toxicity to earthworm reproduction remained essentially unchanged following remediation. Furthermore, phytotoxicity and genotoxicity were higher for the remediated soil compared to the untreated soil. The toxicity remaining after treatment appeared to be due to residual solvent introduced during the remediation process, and/or to heavy metals or other inorganic contaminants not removed by the treatment. Mixture studies involving isopropanol and known toxicants indicated possible synergistic effects of the extraction solvent and soil contaminants. The toxicity in plants was essentially eliminated by a postremediation, water-rinsing step. These results demonstrate a need for including toxicity measurements in the evaluation of technologies used in hazardous waste site remediations, and illustrate the potential value of such measurements for making modifications to remediation processes.

Procedure for cogeneration plant evaluation in Italy

International Nuclear Information System (INIS)

Bollettini, U.; Savelli, D.

1992-01-01

This paper develops a step-by-step approach to the evaluation of cogeneration plants for on-site power generation. The aim is to allow prospective cogeneration plant owners to build energy/cost efficient plants and to be able to make a proper assessment of eligible financial assistance which may be obtained through the provisions of energy conservation normatives and laws set up by the Italian National Energy Plan. The approach has three principal phases - the verification of the availability of the required human resources able to perform the plant evaluation (engineering, legal and business consultants), an energy/viability audit of any existing energy plant considered for retrofitting and, finally, the identification of the best technical/economic cogeneration alternative. The programmed set of evaluation tasks includes the determination of optimal contracts with ENEL (the Italian National Electricity Board), especially for the case of excess power to be ceded to the national grid, and the making of comparisons with reference cogeneration systems whose relative design/cost data are stored in existing computerized data bases

Introducing PCTRAN as an evaluation tool for nuclear power plant emergency responses

International Nuclear Information System (INIS)

Cheng, Yi-Hsiang; Shih, Chunkuan; Chiang, Show-Chyuan; Weng, Tung-Li

2012-01-01

Highlights: ► PCTRAN is integrated with an atmospheric dispersion algorithm. ► The improved PCTRAN acts as an accident/incident simulator and a data exchange system. ► The software helps the responsible organizations decide the rescue and protective actions. ► The evaluation results show the nuclear power plant accident and its off-site dose consequences. ► The software can be used for nuclear power plant emergency responses. - Abstract: Protecting the public from radiation exposure is important if a nuclear power plant (NPP) accident occurs. Deciding appropriate protective actions in a timely and effective manner can be fulfilled by using an effective accident evaluation tool. In our earlier work, we have integrated PCTRAN (Personal Computer Transient Analyzer) with the off-site dose calculation model. In this study, we introduce PCTRAN as an evaluation tool for nuclear power plant emergency responses. If abnormal conditions in the plant are monitored or observed, the plant staffs can distinguish accident/incident initiation events. Thus, the responsible personnel can immediately operate PCTRAN and set up those accident/incident initiation events to simulate the nuclear power plant transient or accident in conjunction with off-site dose distributions. The evaluation results consequently help the responsible organizations decide the rescue and protective actions. In this study, we explain and demonstrate the capabilities of PCTRAN for nuclear emergency responses, through applying it to simulate the postulated nuclear power plant accident scenarios.

Factors of site selection for nuclear power plants in selected industrial states

International Nuclear Information System (INIS)

Hoffmann, L.; Obermair, G.; Ringler, W.; Romahn, B.; Sanders, H.

1978-01-01

The range of the tasks within the project consists of working out an optimal catalogue of criteria for the site selection for nuclear power plants; establishing a structured documentation system for the criteria and licensing procedures used by selected industrial countries when selecting sites for nuclear power plants; analyzing and evaluating the documented material with the aim of supplying the basis for decisions concerning land use. The tasks are being realized within a technological ring of data (for the period until 1990, reactor types, cooling, power-heat coupling, special sites, block sizes, local concentration) and a set politico-economical ring of data for the following countries: F.R. Germany, Belgium, Switzerland, Great Britain, Sweden, Denmark, Austria, France, Netherlands, USA, Japan, Yougoslavia. (HP) [de

Remote sensing for nuclear power plant siting

International Nuclear Information System (INIS)

Siegal, B.S.; Welby, C.W.

1981-01-01

Remote sensing techniques enhance the selection and evaluation process for nuclear power plant siting. The principal advantage is the synoptic view which improves recognition of linear features, possibly indicative of faults. The interpretation of such images, in conjunction with seismological studies, also permits delineation of seismo-tectonic provinces. In volcanic terrains, geomorphic-age boundaries can be delineated and volcanic centers identified, providing necessary guidance for field sampling and regional model derivation. The use of such techniques is considered for studies in the Philippines, Mexico, and Greece. 5 refs

Evaluation of environmental data relating to selected nuclear power plant sites. Prairie Island Nuclear Generating Plant site

International Nuclear Information System (INIS)

Murarka, I.P.

1976-11-01

Environmental monitoring data for 1973 through 1975 pertaining to the Prairie Island Nuclear Generating Station (which began commercial operation in December 1973) were analyzed by the most practical qualitative and quantitative methods. Evaluations of aquatic and terrestrial biotic data are presented in this report. The data indicate no significant immediate deleterious effects on the biota from plant operation, thus confirming preoperational predictions. Although the station has not operated long enough to reveal long-term deleterious effects, present indications do not lead to a concerned prediction that any are developing. Recommendations are suggested for improving monitoring techniques

Site-specific analysis of hybrid geothermal/fossil power plants. Volume One. Roosevelt Hot Springs KGRA

Energy Technology Data Exchange (ETDEWEB)

1977-06-01

The economics of a particular hybrid plant must be evaluated with respect to a specific site. This volume focuses on the Roosevelt Hot Springs KGRA. The temperature, pressure, and flow rate data given suggests the site deserves serious consideration for a hybrid plant. Key siting considerations which must be addressed before an economic judgment can be attempted are presented as follows: the availability, quality, and cost of coal; the availability of water; and the availability of transmission. Seismological and climate factors are presented. (MHR)

Evaluation of sites for the location of WEEE recycling plants in Spain.

Science.gov (United States)

Queiruga, Dolores; Walther, Grit; González-Benito, Javier; Spengler, Thomas

2008-01-01

As a consequence of new European legal regulations for treatment of waste electrical and electronic equipment (WEEE), recycling plants have to be installed in Spain. In this context, this contribution describes a method for ranking of Spanish municipalities according to their appropriateness for the installation of these plants. In order to rank the alternatives, the discrete multi-criteria decision method PROMETHEE (Preference Ranking Organisation METHod for Enrichment Evaluations), combined with a surveys of experts, is applied. As existing plants are located in North and East Spain, a significant concentration of top ranking municipalities can be observed in South and Central Spain. The method does not present an optimal structure of the future recycling system, but provides a selection of good alternatives for potential locations of recycling plants.

Volcanoes and associated topics in relation to nuclear power plant siting

International Nuclear Information System (INIS)

1997-01-01

The main purpose of this report is to provide draft guidance on the criteria and methods for the evaluation of a site for a nuclear power plant with respect to the potential effects of volcanic activity which may jeopardize its safety and to elicit feedback from Member States. Different types of phenomena associated with volcanism are discussed in terms of their influence on site acceptability and on derivation of design basis parameters. This report was developed for application to new nuclear power plant sites. It does not address the issue of the re-evaluation of existing nuclear power sites to the potential effects of volcanic activity, although it contains general information and criteria useful for this purpose. The guidelines and procedures discussed in this report can appropriately be used as the basis for the safe siting and design of nuclear power plants in different volcanic environments. In this report, the description of the phenomena associated with volcanism and the collection of required data and information are separated from the criteria for hazard assessment. Thus Section 2 gives the non-specialist a general description of the different types of volcanic phenomena and Section 4 provides indication on the acquisition of the database. Section 3 outlines the general requirements to be fulfilled during site selection and evaluation. Sections 5, 6 and 7 provide guidance to perform the hazard assessment and to derive the design basis parameters. Finally, Section 8 deals with monitoring systems. As general information for the non-specialist, Annex I provides the major divisions of geological time. With the same spirit, and recognizing that a complete consensus has not been reached in the scientific community on the use and meaning of some terms, a glossary of volcanological definitions is given in Annex II, applicable only to the use of this report. Finally, Annex III provides an example of a classification of volcanoes that may be used for capability

Main phases of siting for nuclear power plants with review of required investigations

International Nuclear Information System (INIS)

Malbasa, N.

1984-01-01

The purpose of the article is a short description of the main phases in the process of siting for nuclear power plants as interpreted and applied by the Institut za elektroprivredu, Zagreb in the screening, comparison and evaluation of the sites for NPPs in the SR of Croatia. The scope and purpose, as well as review of required data and investigations for each particular phase are given. Common used methods for the comparison of sites are described and example of rejection criteria applicable for early phases of the siting is proposed. It is given a list of the most important activities which detailed analysis id indispensable for ending of the evaluation and getting a site permit from the regulatory body. A legal and regulatory basis for carrying out the siting process is also described. (author)

Method for assigning sites to projected generic nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Holter, G.M.; Purcell, W.L.; Shutz, M.E.; Young, J.R.

1986-07-01

Pacific Northwest Laboratory developed a method for forecasting potential locations and startup sequences of nuclear power plants that will be required in the future but have not yet been specifically identified by electric utilities. Use of the method results in numerical ratings for potential nuclear power plant sites located in each of the 10 federal energy regions. The rating for each potential site is obtained from numerical factors assigned to each of 5 primary siting characteristics: (1) cooling water availability, (2) site land area, (3) power transmission land area, (4) proximity to metropolitan areas, and (5) utility plans for the site. The sequence of plant startups in each federal energy region is obtained by use of the numerical ratings and the forecasts of generic nuclear power plant startups obtained from the EIA Middle Case electricity forecast. Sites are assigned to generic plants in chronological order according to startup date.

Method for assigning sites to projected generic nuclear power plants

International Nuclear Information System (INIS)

Holter, G.M.; Purcell, W.L.; Shutz, M.E.; Young, J.R.

1986-07-01

Pacific Northwest Laboratory developed a method for forecasting potential locations and startup sequences of nuclear power plants that will be required in the future but have not yet been specifically identified by electric utilities. Use of the method results in numerical ratings for potential nuclear power plant sites located in each of the 10 federal energy regions. The rating for each potential site is obtained from numerical factors assigned to each of 5 primary siting characteristics: (1) cooling water availability, (2) site land area, (3) power transmission land area, (4) proximity to metropolitan areas, and (5) utility plans for the site. The sequence of plant startups in each federal energy region is obtained by use of the numerical ratings and the forecasts of generic nuclear power plant startups obtained from the EIA Middle Case electricity forecast. Sites are assigned to generic plants in chronological order according to startup date

Nuclear Power Plant project site selection geotechnical considerations

International Nuclear Information System (INIS)

Katti, V.J.; Banerjee, D.C.

1997-01-01

During the selection of a site for Nuclear Power Plant (NPP) and Radioactive Waste Plant (RWP), geotechnical investigations play a significant role in deciding merits and demerits of the sites. Any accidents in these units can play havoc on mankind and may leave bitter imprints on generations to come. Hence proper care has to be taken at the early stage for selecting the sites. Site selection procedure is a complicated one, because it involves experts from various disciplines like geology, geophysics, civil, mechanical electrical engineering, health-physics and other fields

Ames expedited site characterization demonstration at the former manufactured gas plant site, Marshalltown, Iowa

International Nuclear Information System (INIS)

Bevolo, A.J.; Kjartanson, B.H.; Wonder, J.D.

1996-03-01

The goal of the Ames Expedited Site Characterization (ESC) project is to evaluate and promote both innovative technologies (IT) and state-of-the-practice technologies (SOPT) for site characterization and monitoring. In April and May 1994, the ESC project conducted site characterization, technology comparison, and stakeholder demonstration activities at a former manufactured gas plant (FMGP) owned by Iowa Electric Services (IES) Utilities, Inc., in Marshalltown, Iowa. Three areas of technology were fielded at the Marshalltown FMGP site: geophysical, analytical and data integration. The geophysical technologies are designed to assess the subsurface geological conditions so that the location, fate and transport of the target contaminants may be assessed and forecasted. The analytical technologies/methods are designed to detect and quantify the target contaminants. The data integration technology area consists of hardware and software systems designed to integrate all the site information compiled and collected into a conceptual site model on a daily basis at the site; this conceptual model then becomes the decision-support tool. Simultaneous fielding of different methods within each of the three areas of technology provided data for direct comparison of the technologies fielded, both SOPT and IT. This document reports the results of the site characterization, technology comparison, and ESC demonstration activities associated with the Marshalltown FMGP site. 124 figs., 27 tabs

Site-Specific Seismic Site Response Model for the Waste Treatment Plant, Hanford, Washington

Energy Technology Data Exchange (ETDEWEB)

Rohay, Alan C.; Reidel, Steve P.

2005-02-24

This interim report documents the collection of site-specific geologic and geophysical data characterizing the Waste Treatment Plant site and the modeling of the site-specific structure response to earthquake ground motions.

Secondary plant succession on disturbed sites at Yucca Mountain, Nevada

Energy Technology Data Exchange (ETDEWEB)

Angerer, J.P.; Ostler, W.K.; Gabbert, W.D.; Schultz, B.W.

1994-12-01

This report presents the results of a study of secondary plant succession on disturbed sites created during initial site investigations in the late 1970s and early 1980s at Yucca Mountain, NV. Specific study objectives were to determine the rate and success of secondary plant succession, identify plant species found in disturbances that may be suitable for site-specific reclamation, and to identify environmental variables that influence succession on disturbed sites. During 1991 and 1992, fifty seven disturbed sites were located. Vegetation parameters, disturbance characteristics and environmental variables were measured at each site. Disturbed site vegetation parameters were compared to that of undisturbed sites to determine the status of disturbed site plant succession. Vegetation on disturbed sites, after an average of ten years, was different from undisturbed areas. Ambrosia dumosa, Chrysothamnus teretifolius, Hymenoclea salsola, Gutierrezia sarothrae, Atriplex confertifolia, Atriplex canescens, and Stephanomeria pauciflora were the most dominant species across all disturbed sites. With the exception of A. dumosa, these species were generally minor components of the undisturbed vegetation. Elevation, soil compaction, soil potassium, and amounts of sand and gravel in the soil were found to be significant environmental variables influencing the species composition and abundance of perennial plants on disturbed sites. The recovery rate for disturbed site secondary succession was estimated. Using a linear function (which would represent optimal conditions), the recovery rate for perennial plant cover, regardless of which species comprised the cover, was estimated to be 20 years. However, when a logarithmic function (which would represent probable conditions) was used, the recovery rate was estimated to be 845 years. Recommendations for future studies and site-specific reclamation of disturbances are presented.

Secondary plant succession on disturbed sites at Yucca Mountain, Nevada

International Nuclear Information System (INIS)

Angerer, J.P.; Ostler, W.K.; Gabbert, W.D.; Schultz, B.W.

1994-12-01

This report presents the results of a study of secondary plant succession on disturbed sites created during initial site investigations in the late 1970s and early 1980s at Yucca Mountain, NV. Specific study objectives were to determine the rate and success of secondary plant succession, identify plant species found in disturbances that may be suitable for site-specific reclamation, and to identify environmental variables that influence succession on disturbed sites. During 1991 and 1992, fifty seven disturbed sites were located. Vegetation parameters, disturbance characteristics and environmental variables were measured at each site. Disturbed site vegetation parameters were compared to that of undisturbed sites to determine the status of disturbed site plant succession. Vegetation on disturbed sites, after an average of ten years, was different from undisturbed areas. Ambrosia dumosa, Chrysothamnus teretifolius, Hymenoclea salsola, Gutierrezia sarothrae, Atriplex confertifolia, Atriplex canescens, and Stephanomeria pauciflora were the most dominant species across all disturbed sites. With the exception of A. dumosa, these species were generally minor components of the undisturbed vegetation. Elevation, soil compaction, soil potassium, and amounts of sand and gravel in the soil were found to be significant environmental variables influencing the species composition and abundance of perennial plants on disturbed sites. The recovery rate for disturbed site secondary succession was estimated. Using a linear function (which would represent optimal conditions), the recovery rate for perennial plant cover, regardless of which species comprised the cover, was estimated to be 20 years. However, when a logarithmic function (which would represent probable conditions) was used, the recovery rate was estimated to be 845 years. Recommendations for future studies and site-specific reclamation of disturbances are presented

Applications of SLAR in nuclear power plant siting: A case history

Science.gov (United States)

Siegal, B. S.

1980-01-01

Over 10,000 square km of side-looking airborne radar (SLAR) imagery was obtained and analyzed for the siting of the first nuclear power plant in the Republic of the Philippines. The imagery was obtained using the Motorola APS/AN-94D (X-band) real aperture system as part of an overall remote sensing program to site and evaluate potential site regions. Analysis of SLAR images, in conjunction with LANDSAT, color, black and white, and thermal infrared images, provided basic information on structure, relative geochronology, stratigraphy, geomorphology, and ground water, which facilitated field operations and data synthesis.

Optimal Procedure for siting of Nuclear Power Plant

International Nuclear Information System (INIS)

Aziuddin, Khairiah Binti; Park, Seo Yeon; Roh, Myung Sub

2013-01-01

This study discusses on a simulation approach for sensitivity analysis of the weights of multi-criteria decision models. The simulation procedures can also be used to aid the actual decision process, particularly when the task is to select a subset of superior alternatives. This study is to identify the criteria or parameters which are sensitive to the weighting factor that can affect the results in the decision making process to determine the optimal site for nuclear power plant (NPP) site. To perform this study, we adhere to IAEA NS-R-3 and DS 433. The siting process for nuclear installation consists of site survey and site selection stages. The siting process generally consists of an investigation of a large region to select one or more candidate sites by surveying the sites. After comparing the ROI, two candidate sites are compared for final determination, which are Wolsong and Kori site. Some assumptions are taken into consideration due to limitations and constraints throughout performing this study. Sensitivity analysis of multi criteria decision models is performed in this study to determine the optimal site in the site selection stage. Logical Decisions software will be employed as a tool to perform this analysis. Logical Decisions software helps to formulate the preferences and then rank the alternatives. It provides clarification of the rankings and hence aids the decision makers on evaluating the alternatives, and finally draw a conclusion on the selection of the optimal site

Optimal Procedure for siting of Nuclear Power Plant

Energy Technology Data Exchange (ETDEWEB)

Aziuddin, Khairiah Binti; Park, Seo Yeon; Roh, Myung Sub [KEPCO International Nuclear Graduate School, Ulsan (Korea, Republic of)

2013-10-15

This study discusses on a simulation approach for sensitivity analysis of the weights of multi-criteria decision models. The simulation procedures can also be used to aid the actual decision process, particularly when the task is to select a subset of superior alternatives. This study is to identify the criteria or parameters which are sensitive to the weighting factor that can affect the results in the decision making process to determine the optimal site for nuclear power plant (NPP) site. To perform this study, we adhere to IAEA NS-R-3 and DS 433. The siting process for nuclear installation consists of site survey and site selection stages. The siting process generally consists of an investigation of a large region to select one or more candidate sites by surveying the sites. After comparing the ROI, two candidate sites are compared for final determination, which are Wolsong and Kori site. Some assumptions are taken into consideration due to limitations and constraints throughout performing this study. Sensitivity analysis of multi criteria decision models is performed in this study to determine the optimal site in the site selection stage. Logical Decisions software will be employed as a tool to perform this analysis. Logical Decisions software helps to formulate the preferences and then rank the alternatives. It provides clarification of the rankings and hence aids the decision makers on evaluating the alternatives, and finally draw a conclusion on the selection of the optimal site.

Pollution prevention opportunity assessment for the K-25 Site Steam Plant -- Level 3

International Nuclear Information System (INIS)

1995-09-01

A Level 3 pollution prevention opportunity assessment (PPOA) was performed for the K-1501 Steam Plant at the K-25 Site. The primary objective was to identify and evaluate pollution prevention (P2) options to reduce the quantities of each waste stream generated by the Steam Plant. For each of the waste streams, P2 options were evaluated to first reduce the quantity of waste generated and second to recycle the waste. This report provides a process description of the facility; identification, evaluation, and recommendations of P2 options; an implementation schedule with funding sources; and conclusions. Largely for economic reasons, only 3 of the 14 P2 options are being recommended for implementation. All are source reduction options. When implemented, these three options are estimated to reduce the annual generation of waste by 658,412 kg and will result in a cost savings of approximately $29,232/year for the K-25 Site. The recommended options are to: install a flue gas return System in Boiler 7; reduce steam loss from traps; and increase lapse time between rinses. The four boilers currently in operation at the Steam Plant use natural gas or fuel oil as fuel sources

Early Site Permit Demonstration Program: Plant parameters envelope report

International Nuclear Information System (INIS)

1993-03-01

The Early Site Permit (ESP) Demonstration Program is the nuclear industry's initiative for piloting the early resolution of siting-related issues before the detailed design proceedings of the combined operating license review. The ESP Demonstration Program consists of three phases. The plant parameters envelopes task is part of Phase 1, which addresses the generic review of applicable federal regulations and develops criteria for safety and environmental assessment of potential sites. The plant parameters envelopes identify parameters that characterize the interface between an ALWR design and a potential site, and quantify the interface through values selected from the Utility Requirements Documents, vendor design information, or engineering assessments. When augmented with site-specific information, the plant parameters envelopes provide sufficient information to allow ESPs to be granted based on individual ALWR design information or enveloping design information for the evolutionary, passive, or generic ALWR plants. This document is expected to become a living document when used by future applicants

Quantitative comparison of the nuclear power plant sites in the United Kingdom

Energy Technology Data Exchange (ETDEWEB)

Shaw, J; Sina, A M [Queen Mary Coll., London (UK). Dept. of Nuclear Engineering

1976-01-01

A probabilistic method is described for a comparison of nuclear power plant sites in the United Kingdom, which evaluates quantitatively the sites in terms of favourability, by taking into account the real term meteorological conditions, i.e. wind direction, wind speed, and stability distributions, and also the population distribution around the cities. A 'site safety quality factor' is obtained for each site and is used to compare the favourability of each site with respect to releases of radioactivity. The quality factor corresponds to the average number of persons that would be exposed to the specified relative concentration averaged over all weather conditions. The sites compared are Berkeley, Bradwell, Dungeness, Hartlepool, Heysham, Oldbury, Sizewell, and Wylfa.

ITER plant layout and site services

International Nuclear Information System (INIS)

Chuyanov, V.A.

2000-01-01

The ITER site has not yet been determined. Nevertheless, to develop a construction plan and a cost estimate, it is necessary to have a detailed layout of the buildings, structures and outdoor equipment integrated with the balance of plant service systems prototypical of large fusion power plants. These services include electrical power for magnet feeds and plasma heating systems, cryogenic and conventional cooling systems, compressed air, gas supplies, demineralized water, steam and drainage. Nuclear grade facilities are provided to handle tritium fuel and activated waste, as well as to prevent radiation exposure of workers and the public. To prevent interference between services of different types and for efficient arrangement of buildings, structures and equipment within the site area, a plan was developed which segregated different classes of services to four quadrants surrounding the tokamak building, placed at the approximate geographical centre of the site. The locations of the buildings on the generic site were selected to meet all design requirements at minimum total project cost. A similar approach was used to determine the locations of services above, at and below grade. The generic site plan can be adapted to the site selected for ITER without significant changes to the buildings or equipment. Some rearrangements may be required by site topography, resulting primarily in changes to the length of services that link the buildings and equipment. (author)

Test program for closure activities at a mixed waste disposal site at the Savannah River Plant

International Nuclear Information System (INIS)

Cook, J.R.; Harley, J.P. Jr.

1988-01-01

A 58-acre site at the Savannah River Plant which was used for disposal of low-level radioactive waste and quantities of the hazardous materials lead, cadmium, scintillation fluid, and oil will be the first large waste site at the Savannah River Plant to be permanently closed. The actions leading to closure of the facility will include surface stabilization and capping of the site. Test programs have been conducted to evaluate the effectiveness of dynamic compaction as a stabilization technique and the feasibility of using locally derived clay as a capping material

On-site tests on the nuclear power plants

International Nuclear Information System (INIS)

Morilhat, P.; Favennec, J.M.; Neau, P.; Preudhomme, E.

1996-01-01

On-site tests and experiments are performed by EDF Research and Development Division on the nuclear power plants to assess the behaviour of major components submitted to thermal and vibratory solicitations. On-going studies deal with the qualification of new nuclear power plant standard and with the feedback of plants under operation. The tests, particularly the investigation tests, correspond to large investments and entail an important data volume which must ensure the continuity over a long period of the order of magnitude of the in-service plant life (around 40 years). This paper addresses the on-site experimental activities, describes the means to be used, and gives an example: the qualification of SG of new 1450 MW nuclear power plants. (author)

Probabilistic siting analysis of nuclear power plants emphasizing atmospheric dispersion of radioactive releases and radiation-induced health effects

International Nuclear Information System (INIS)

Savolainen, Ilkka

1980-01-01

A presentation is made of probabilistic evaluation schemes for nuclear power plant siting. Effects on health attributable to ionizing radiation are reviewed, for the purpose of assessment of the numbers of the most important health effect cases in light-water reactor accidents. The atmospheric dispersion of radioactive releases from nuclear power plants is discussed, and there is presented an environmental consequence assessment model in which the radioactive releases and atmospheric dispersion of the releases are treated by the application of probabilistic methods. In the model, the environmental effects arising from exposure to radiation are expressed as cumulative probability distributions and expectation values. The probabilistic environmental consequence assessment model has been applied to nuclear power plant site evaluation, including risk-benefit and cost-benefit analyses, and the comparison of various alternative sites. (author)

Seismic PSA method for multiple nuclear power plants in a site

Energy Technology Data Exchange (ETDEWEB)

Hakata, Tadakuni [Nuclear Safety Commission, Tokyo (Japan)

2007-07-15

The maximum number of nuclear power plants in a site is eight and about 50% of power plants are built in sites with three or more plants in the world. Such nuclear sites have potential risks of simultaneous multiple plant damages especially at external events. Seismic probabilistic safety assessment method (Level-1 PSA) for multi-unit sites with up to 9 units has been developed. The models include Fault-tree linked Monte Carlo computation, taking into consideration multivariate correlations of components and systems from partial to complete, inside and across units. The models were programmed as a computer program CORAL reef. Sample analysis and sensitivity studies were performed to verify the models and algorithms and to understand some of risk insights and risk metrics, such as site core damage frequency (CDF per site-year) for multiple reactor plants. This study will contribute to realistic state of art seismic PSA, taking consideration of multiple reactor power plants, and to enhancement of seismic safety. (author)

Sites and social assessment of nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Nemoto, K [Central Research Inst. of Electric Power Industry, Tokyo (Japan)

1977-09-01

The sites of nuclear power plants in Japan have two features, first the extreme expectation for regional development because of the selection of depopulated districts for most locations, and the second, apprehensions of local people for two reasons of nuclear power generating techniques which do not plant the roots in society and handling of radioactive materials. In order to cope with these problems, it is necessary to consider that the development plan of the regions around reactor sites must be compiled systematically. Its premise is the ''social assessment'' which estimates the economical and social influences and evaluates the merit and demerit of nuclear power plants prior to the construction. This is of course inevitable. The objects of the assessment may be divided as follows: the human effect to individuals, the institutional effect to local community, the economical effect to region, and the national influence to the whole country. While the developmental action of locations includes the stages of examination, planning, construction and operation, and three location patterns are recognized according to the emphasized function, the improvement of national economy, upgrading of environmental quality, and the most priority in local welfare. In the process of the assessment, the following items may be taken notice that each item requires sometimes the weighting; the pattern to abandon location may exist; positive and negative effects are required to be distributed evenly in a triangle having the apexes each representing one of the above three patterns.

Hypothesis of a nuclear accident to the nuclear power plant of Gravelines with important radioactive release out of the site: risks prevention, intervention strategies. Evaluation of the sensitization to the nuclear risk of the physician practicing near the site

International Nuclear Information System (INIS)

Mraovic, Th.

1998-01-01

This thesis has for hypothesis a nuclear accident at the nuclear power plant of Gravelines with radioactive release out of the site: the risks prevention and the strategies of intervention are studied. An evaluation of the sensitization to a nuclear risk is made for the general practitioner that practices near the site. (N.C.)

Underground siting of nuclear power plants

International Nuclear Information System (INIS)

Bender, F.

1982-01-01

The symposium gave the opportunity for an international exchange of views on the concepts of underground nuclear power plants, which are presently world wide under consideration. The results of investigations into the advantages and disadvantages with regard to the technical safety aspects of the underground plants in comparison to plants on the surface led to open and sometimes controversal discussions. As a result of the symposium (32 contributions) a general agreement can be stated on the judgement concerning the advantages and the disadvantages of underground nuclear power plants (nnp). The advantages are: increased protection against external events; delayed release of fission products in accident situations, if the closures operate properly. The disadvantages are: increased costs of the construction of underground and restrictions to such sites where either large caverns or deep pits can be constructed, which also requires that certain technical problems must be solved beforehand. Also, additional safety certificates related to the site will be required within the licensing procedures. The importance of these advantages and disadvantages was in some cases assessed very differently. The discussions also showed, that there are a number of topics where some questions have not been finally answered yet. (orig./HP) [de

Biological fluidized-bed treatment of groundwater from a manufactured gas plant site

International Nuclear Information System (INIS)

Grey, G.M.; Scheible, O.K.; Maiello, J.A.; Guarini, W.J.; Sutton, P.M.

1995-01-01

Bench- and pilot-scale biological treatability studies were performed as part of a comprehensive study for developing an on-site treatment system for contaminated groundwater at a former manufactured gas plant site. The bench-scale work, which included evaluations of activated sludge and fluidized-bed biological processes, indicated that a carbon-based fluidized-bed process was most appropriate. The process was then demonstrated on a pilot level at the site. The bench and pilot studies demonstrated significant reductions of chemical oxygen demand (COD), and all target organics including polycyclic aromatic hydrocarbons (PAHs) and volatile organic compounds (VOCs)

Evaluating biological transport of radionuclides at low-level waste burial sites

International Nuclear Information System (INIS)

Cadwell, L.L.; Kennedy, W.E.; McKenzie, D.H.

1983-08-01

The purpose of the work reported here is to develop and demonstrate methods for evaluating the long-term impact of biological processes at low-level waste (LLW) disposal sites. As part of this effort, we developed order-of-magnitude estimates of dose-to-man resulting from animal burrowing activity and plant translocation of radionuclides. Reference low-level waste sites in both arid and humid areas of the United States were examined. The results of our evaluation for generalized arid LLW burial site are presented here. Dose-to-man estimates resulting from biotic transport are compared with doses calculated from human intrusion exposure scenarios. Dose-to-man estimates, as a result of biotic transport, are of the same order of magnitude as those resulting from a more commonly evaluated human intrusion scenario. The reported lack of potential importance of biotic transport at LLW sites in earlier assessment studies is not confirmed by our findings. These results indicate that biotic transport has the long-term potential to mobilize radionuclides. Therefore, biotic transport should be carefully evaluated during burial site assessment

In-situ solidification cleans up old gas plant site

International Nuclear Information System (INIS)

Hatfield, A.D.; Dennis, N.D.

1995-01-01

A manufactured gas plant site in Columbus, Georgia, was the location of an environmental cleanup in 1992. Manufactured gas was produced at this site from 1854 to 1931 with the availability of natural gas from a transmission pipeline causing its demise. However, waste products, primarily coal tar from the earlier years of plant operation, remained with the site. In-situ solidification was chosen as the cleanup method. Post monitoring activities show that the project was successful and the site is now a park and a leading part of river front development

Rock siting of nuclear power plants from a reactor safety standpoint

International Nuclear Information System (INIS)

1975-11-01

The study has aimed at surveying the advantages and disadvantages of a rock sited nuclear power plant from a reactor safety standpoint. The studies performed are almost entirely concentrated on the BWR alternative. The design of a nuclear power plant in rock judged most appropriate has been studied in greater detail, and a relatively extensive safety analysis has been made. It is found that the presented technical design of the rock sited alternative is sufficiently advanced to form a basis for further projecting treatment. The chosen technical design of the reactor plant demands a cavern with a 45-50 metre span. Caverns without strengthening efforts with such spans are used in mines, but have no previously been used for industrial plants. Studies of the stability of such caverns show that a safety level is attainable corresponding to the safety required for the other parts of the nuclear power plant. The conditions are that the rock is of high quality, that necessary strengthening measures are taken and that careful studies of the rock are made before and during the blasting, and also during operation of the plant. When locating a rock sited nuclear power plant, the same criteria must be considered as for an above ground plant, with additional stronger demands for rock quality. The presented rock sited nuclear power plant has been assessed to cost 20 % more in total construction costs than a corresponding above ground plant. The motivations for rock siting also depend on whether a condensing plant for only electricity production, or a plant for combined power production and district heating, is considered. The latter would under certain circumstances make rock siting look more attractive. (author)

A method of risk assessment for a multi-plant site

International Nuclear Information System (INIS)

White, R.F.

1983-06-01

A model is presented which can be used in conjunction with probabilistic risk assessment to estimate whether a site on which there are several plants (reactors or chemical plants containing radioactive materials) meets whatever risk acceptance criteria or numerical risk guidelines are applied at the time of the assessment in relation to various groups of people and for various sources of risk. The application of the multi-plant site model to the direct and inverse methods of risk assessment is described. A method is proposed by which the potential hazard rating associated with a given plant can be quantified so that an appropriate allocation can be made when assessing the risks associated with each of the plants on a site. (author)

Solvent extraction for remediation of manufactured gas plant sites

International Nuclear Information System (INIS)

Luthy, R.G.; Dzombak, D.A.; Peters, C.; Ali, M.A.; Roy, S.B.

1992-12-01

This report presents the results of an initial assessment of the feasibility of solvent extraction for removing coal tar from the subsurface or for treating contaminated soil excavated at manufactured gas plant (MGP) sites. In situ solvent extraction would involve injection, recovery, and reclamation for reinjection of an environmentally-benign, water-miscible solvent. Accelerated dissolution and removal of coaltar from the subsurface might be desirable as a remedial approach if excavation is not practical (e.g., the site underlies facilities in current use), direct pumping of coal tar is ineffective, and bioremediation is not feasible because of the presence of high concentrations of coal tar. Both laboratory experiments and engineering evaluations were performed to provide a basis for the initial feasibility assessment. Laboratory work included identification and evaluation of promising solvents, measurement of fundamental properties of coal tar-solvent-water systems, and measurement of rates of dissolution of coal tar in porous media into flowing solvent-water solutions. Engineering evaluations involved identification of common hydrogeologic features and contaminant distributions at MGP sites, and identification and evaluation of possible injection-recovery well deployment schemes. A coupled flow-chemistry model was developed for simulation of the in situ process and evaluation of the well deployment schemes. Results indicate that in situsolvent extraction may be able to recover a significant amount of coal tar from the subsurface within a reasonable time frame (on the order of one year or so) provided that subsurface conditions are conducive to process implementation. Some important implementation issues remain to be addressed

Design of quality assurance surveillance of geotechnical investigation in evaluation of nuclear power plants siting

International Nuclear Information System (INIS)

Made Pramayuni; Haendra Subekti

2011-01-01

System of building Nuclear Power Plants (NPP) is built above ground surface and rocks. Therefore, the geotechnical aspects evaluation of NPP siting in particular must be implemented properly and accurately. The successful of the design and construction of the building system is influenced by geotechnical conditions in the vicinity of NPP will be built. To be able to perform geotechnical analysis is good and true; it's required data of surface/underground completely. These data can be obtained directly not only from the geotechnical field investigations, but also can be obtained from the laboratory tests results. To ensure that geotechnical investigations are conducted effectively and efficiently, produce accurate data, as well as meeting the requirements of safety, health, safety, environmental, quality and economic, then the Quality Assurance Program (QAP) should be established and implemented. Supervision of the QAP implementation is required to ensure the work is done according to QAP that have been established and applicable requirement. (author)

Part 2: Conserving and Planting Trees at Development Sites

Science.gov (United States)

Karen Cappiella; Tom Schueler; Tiffany Wright

2006-01-01

This manual presents specific ways to enable developers, engineers or landscape architects to incorporate more trees into a development site. The proposed approach focuses on protecting existing trees, planting trees in storm water treatment practices, and planting trees in other open spaces at the development site. This manual introduces conceptual designs for storm...

Design basis flood for nuclear power plants on river sites

International Nuclear Information System (INIS)

1983-01-01

The Guide presents techniques for determining the design basis flood (DBF) to be used for siting nuclear power plants at or near non-tidal reaches of rivers and for protecting nuclear power plants against floods. Since flooding of a nuclear power plant can have repercussions on safety, the DBF is always chosen to have a very low probability of exceedance per annum. The DBF may result from one or more of the following causes: (1) Precipitation, snowmelt; (2) Failure of water control structures, either from seismic or hydrological causes or from faulty operation of these structures; (3) Channel obstruction such as landslide, ice effects, log or debris jams, and effects of vulcanism. Normally the DBF is not less than any recorded or historical flood occurrence. For flood evaluation two types of methods are discussed in this Guide: probabilistic and deterministic. Simple probabilistic methods to determine floods of such low exceedance probability have a great degree of uncertainty and are presented for use only during the site survey. However, the more sophisticated probabilistic methods, the so-called stochastic methods, may give an acceptable result, as outlined in this Guide. The preferred method of evaluating the component of the DBF due to precipitation, as described in this Guide, is the deterministic one, based on the concept of a limit to the probable maximum precipitation (PMP) and on the unit hydrograph technique. Dam failures may generate a flood substantially more severe than that due to precipitation. The methodology for evaluating these types of floods is therefore presented in this Guide. Making allowance for the possible simultaneous occurrence of two or more important flood-producing events is also discussed here. The Guide does not deal with floods caused by sabotage

Geological and geotechnical investigations for nuclear power plants sites

International Nuclear Information System (INIS)

Alves, P.R.R.

1984-09-01

This dissertation presents a general methodology for the tasks of geological and geotechnical investigations, to be performed in the proposed sites for construction of nuclear Power Plants. In this work, items dealing with the standards applied to licensing of Nuclear Power Plants, with the selection process of sites and identification of geological and geotechnical parameters needed for the regional and local characterization of the area being studied, were incorporated. This dissertation also provides an aid to the writing of Technical Reports, which are part of the documentation an owner of a Nuclear Power Plant needs to submit to the Comissao Nacional de Energia Nuclear, to fulfill the nuclear installation licensing requirements. Moreover, this work can contribute to the planning of field and laboratory studies, needed to determine the parameters of the area under investigation, for the siting of Nuclear Power Plants. (Author) [pt

Multi-criteria GIS-based siting of an incineration plant for municipal solid waste.

Science.gov (United States)

Tavares, Gilberto; Zsigraiová, Zdena; Semiao, Viriato

2011-01-01

Siting a municipal solid waste (MSW) incineration plant requires a comprehensive evaluation to identify the best available location(s) that can simultaneously meet the requirements of regulations and minimise economic, environmental, health, and social costs. A spatial multi-criteria evaluation methodology is presented to assess land suitability for a plant siting and applied to Santiago Island of Cape Verde. It combines the analytical hierarchy process (AHP) to estimate the selected evaluation criteria weights with Geographic Information Systems (GIS) for spatial data analysis that avoids the subjectivity of the judgements of decision makers in establishing the influences between some criteria or clusters of criteria. An innovative feature of the method lies in incorporating the environmental impact assessment of the plant operation as a criterion in the decision-making process itself rather than as an a posteriori assessment. Moreover, a two-scale approach is considered. At a global scale an initial screening identifies inter-municipal zones satisfying the decisive requirements (socio-economic, technical and environmental issues, with weights respectively, of 48%, 41% and 11%). A detailed suitability ranking inside the previously identified zones is then performed at a local scale in two phases and includes environmental assessment of the plant operation. Those zones are ranked by combining the non-environmental feasibility of Phase 1 (with a weight of 75%) with the environmental assessment of the plant operation impact of Phase 2 (with a weight of 25%). The reliability and robustness of the presented methodology as a decision supporting tool is assessed through a sensitivity analysis. The results proved the system effectiveness in the ranking process. Copyright © 2011 Elsevier Ltd. All rights reserved.

Power plant site evaluation, electric energy demand forecasts - Douglas Point Site. Volume 3. Final report

International Nuclear Information System (INIS)

Wilson, J.W.

1975-07-01

This is part of a series of reports containing an evaluation of the proposed Douglas Point nuclear generating station site located on the Potomac River in Maryland 30 miles south of Washington, D.C. This report contains chapters on the Potomac Electric Power Company's market, forecasting future demand, modelling, a residential demand model, a nonresidential demand model, the Southern Maryland Electric Cooperative Model, short term predictive accuracy, and total system requirements

Engineering evaluation/cost analysis for the proposed management of 15 nonprocess buildings (15 series) at the Weldon Spring Site Chemical Plant, Weldon Spring, Missouri

International Nuclear Information System (INIS)

MacDonell, M.M.; Peterson, J.M.

1991-11-01

The US Department of Energy, under its Surplus Facilities Management Program (SFMP), is responsible for cleanup activities at the Weldon Spring site, located near Weldon Spring, Missouri. The site consists of two noncontiguous areas: (1) a raffinate pits and chemical plant area and (2) a quarry. This engineering evaluation/cost analysis (EE/CA) report has been prepared to support a proposed removal action to manage 15 nonprocess buildings, identified as the 15 Series buildings, at the chemical plant on the Weldon Spring site. These buildings have been nonoperational for more than 20 years, and the deterioration that has occurred during this time has resulted in a potential threat to site workers, the general public, and the environment. The EE/CA documentation of this proposed action is consistent with guidance from the US Environmental Protection Agency (EPA) that addresses removal actions at sites subject to the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) of 1980, as amended by the Superfund Amendments and Reauthorization Act of 1986. Actions at the Weldon Spring site are subject to CERCLA requirements because the site is on the EPA's National Priorities List. The objectives of this report are to (1) identify alternatives for management of the nonprocess buildings; (2) document the selection of response activities that will mitigate the potential threat to workers, the public, and the environment associated with these buildings; and (3) address environmental impact associated with the proposed action

Evaluation of the impact of a committed site on fusion reactor development

International Nuclear Information System (INIS)

Reid, R.L.; Nagy, A.

1979-01-01

The technical and economic merits of a committed fusion site for development of tokamak, mirror, and EBT reactor from ignition through demo phases were evaluated. Schedule compression resulting from evolving several reactor concepts and/or phases on a committed site as opposed to sequential use of independent sites was estimated. Land, water, and electrical power requirements for a committed fusion site were determined. A conceptual plot plan for siting three fusion reactors on a committed site was configured. Reactor support equipment common to the various concepts was identified as candidates for sharing. Licensing issues for fusion plants were briefly addressed

Assessment of drinking water quality around Kudankulam nuclear power plant site using fuzzy synthetic evaluation

International Nuclear Information System (INIS)

Ramesh, S.; Pratheeba, V.; Murugesan, A.G.; Dahiya, S.

2007-01-01

A method based on concept of fuzzy set theory is used for decision-making in the assessment of physicochemical quality of drinking water. Conventional method for water quality assessment does not consider the uncertainties involved either in measurement of water quality parameters or in the limits provided by the regulatory bodies. Fuzzy synthetic evaluation model gives the certainty levels for the quality class of the water based on the prescribed limit of various regulatory bodies and opinion of the experts from the field of drinking water quality. In this paper application of fuzzy rule based method is illustrated with twelve drinking water samples from the residential locality in the vicinity of Kudankulam Nuclear Power Plant site. These samples were analysed for fifteen different physico-chemical parameters, out of them eleven important parameters were used for the quality assessment using fuzzy synthetic evaluation approach. From this study. it has been concluded that out of 12 samples seven are in desirable category with certainty level of 53-100 percent and rest of the samples belongs to acceptable category whose certainty level ranges from 67 to 96 percent. Water from these sources can be used for the drinking purpose if alternate water source is not available without any health concern on the basis of physicochemical characteristics. (author)

Seismic evaluation of existing nuclear power plants

International Nuclear Information System (INIS)

2003-01-01

The IAEA nuclear safety standards publications address the site evaluation and the design of new nuclear power plants (NPPs), including seismic hazard assessment and safe seismic design, at the level of the Safety Requirements as well as at the level of dedicated Safety Guides. It rapidly became apparent that the existing nuclear safety standards documents were not adequate for handling specific issues in the seismic evaluation of existing NPPs, and that a dedicated document was necessary. This is the purpose of this Safety Report, which is written in the spirit of the nuclear safety standards and can be regarded as guidance for the interpretation of their intent. Worldwide experience shows that an assessment of the seismic capacity of an existing operating facility can be prompted for the following: (a) Evidence of a greater seismic hazard at the site than expected before, owing to new or additional data and/or to new methods; (b) Regulatory requirements, such as periodic safety reviews, to ensure that the plant has adequate margins for seismic loads; (c) Lack of anti-seismic design or poor anti-seismic design; (d) New technical finding such as vulnerability of some structures (masonry walls) or equipment (relays), other feedback and new experience from real earthquakes. Post-construction evaluation programmes evaluate the current capability of the plant to withstand the seismic concern and identify any necessary upgrades or changes in operating procedures. Seismic qualification is distinguished from seismic evaluation primarily in that seismic qualification is intended to be performed at the design stage of a plant, whereas seismic evaluation is intended to be applied after a plant has been constructed. Although some guidelines do exist for the evaluation of existing NPPs, these are not established at the level of a regulatory guide or its equivalent. Nevertheless, a number of existing NPPs throughout the world have been and are being subjected to review of their

Summary of wind data from nuclear power plant sites. [USA

Energy Technology Data Exchange (ETDEWEB)

Verholek, M. G.

1977-03-01

A summary of wind data from nuclear power plant sites is presented. National Weather Service archives are an immediately obvious source of wind data, but additional data sources are also available. Utility companies proposing to build nuclear power plants are required to establish on-site meteorological monitoring programs that include towers for collecting wind and temperature data for use in environmental impact assessments. These data are available for more than one hundred planned or operating nuclear power plant sites. A list of the sites, by state, is provided in Appendix A, while Appendix B contains an alphabetical list of the sites. This site wind data provides a valuable addition to the existing NWS data sets, and significantly enlarges the multilevel data presently available. The wind data published through the NRC is assembled and assessed here in order to provide a supplement to existing data sets.

Geoscientific evaluation factors and criteria for siting and site evaluation. Progress report

International Nuclear Information System (INIS)

Stroem, A.; Ericsson, Lars O.; Svemar, C.; Almen, K.E.; Andersson, Johan

1999-03-01

The purposes of the present report are to: present the work that has been done to identify the parameters that need to be determined in a geoscientific site investigation and that serve as the basis for the work with geoscientific evaluation factors; give a progress report from the project that was initiated in 1997 named Siting Factors and Criteria for Site Evaluation, with an emphasis on definitions, outline and structure for the execution of the work; present geoscientific requirements on function both general and in detail in the form of an example for the discipline rock mechanics; present geoscientific evaluation factors associated with different stages in the siting work in the form of an example for the discipline hydrogeochemical composition; present plans for further work as regards criteria for site evaluation in different siting stages. The project is under way, and this is to be regarded as a progress report since e.g. criteria for site evaluation will be presented at a later date. The long-term performance and safety of the deep repository must always be evaluated by means of an integrated safety assessment. The work with factors and criteria can never take the place of such an assessment, but can provide guidance regarding its outcome. Requirements and preferences regarding the function of the rock in the deep repository have been clarified in this progress report. What is new here is the structuring that has been carried out, with a classification into different geoscientific disciplines, and the formalism that has been given to the terms requirement, preference and function. Based on fundamental safety and construction functions, requirements on function have been specified for the disciplines geology, thermal properties, hydro-geology, rock mechanics, chemistry and transport properties. Furthermore, function analyses have been identified by means of which it is possible to concretize requirements on function and which geoscientific parameters are

Geoscientific evaluation factors and criteria for siting and site evaluation. Progress report

Energy Technology Data Exchange (ETDEWEB)

Stroem, A.; Ericsson, Lars O.; Svemar, C. [Swedish Nuclear Fuel and Waste Management Co., Stockholm (Sweden); Almen, K.E. [KEA GEO-konsult AB (Sweden); Andersson, Johan [Golder Grundteknik KB (Sweden)

1999-03-01

The purposes of the present report are to: present the work that has been done to identify the parameters that need to be determined in a geoscientific site investigation and that serve as the basis for the work with geoscientific evaluation factors; give a progress report from the project that was initiated in 1997 named Siting Factors and Criteria for Site Evaluation, with an emphasis on definitions, outline and structure for the execution of the work; present geoscientific requirements on function both general and in detail in the form of an example for the discipline rock mechanics; present geoscientific evaluation factors associated with different stages in the siting work in the form of an example for the discipline hydrogeochemical composition; present plans for further work as regards criteria for site evaluation in different siting stages. The project is under way, and this is to be regarded as a progress report since e.g. criteria for site evaluation will be presented at a later date. The long-term performance and safety of the deep repository must always be evaluated by means of an integrated safety assessment. The work with factors and criteria can never take the place of such an assessment, but can provide guidance regarding its outcome. Requirements and preferences regarding the function of the rock in the deep repository have been clarified in this progress report. What is new here is the structuring that has been carried out, with a classification into different geoscientific disciplines, and the formalism that has been given to the terms requirement, preference and function. Based on fundamental safety and construction functions, requirements on function have been specified for the disciplines geology, thermal properties, hydro-geology, rock mechanics, chemistry and transport properties. Furthermore, function analyses have been identified by means of which it is possible to concretize requirements on function and which geoscientific parameters are

Annual stability evaluation of Waste Isolation Pilot Plant

International Nuclear Information System (INIS)

1993-06-01

A stability evaluation of the underground workings of the Waste Isolation Pilot Plant (WIPP) was completed by the US Bureau of Mines' WIPP evaluation committee. This work included a critical evaluation of the processes employed at WIPP to ensure stability, an extensive review of available deformation measurements, a 3-day site visit, and interviews with the Department of Energy (DOE) and Westinghouse staff. General ground control processes are in place at WIPP to minimize the likelihood that major stability problems will go undetected. To increase confidence in both short- and long-term stability throughout the site (underground openings and shafts), ground stability monitoring systems, mine layout design, support systems and data analyses must be continuously improved. Such processes appear to be in place at WIPP and are discussed in this paper

Seismic Hazards in Site Evaluation for Nuclear Installations. Specific Safety Guide

Energy Technology Data Exchange (ETDEWEB)

NONE

2010-08-15

This Safety Guide was prepared under the IAEA programme for safety standards for nuclear installations. It supplements the Safety Requirements publication on Site Evaluation for Nuclear Installations. The present publication provides guidance and recommends procedures for the evaluation of seismic hazards for nuclear power plants and other nuclear installations. It supersedes Evaluation of Seismic Hazards for Nuclear Power Plants, IAEA Safety Standards Series No. NS-G-3.3 (2002). In this publication, the following was taken into account: the need for seismic hazard curves and ground motion spectra for the probabilistic safety assessment of external events for new and existing nuclear installations; feedback of information from IAEA reviews of seismic safety studies for nuclear installations performed over the previous decade; collective knowledge gained from recent significant earthquakes; and new approaches in methods of analysis, particularly in the areas of probabilistic seismic hazard analysis and strong motion simulation. In the evaluation of a site for a nuclear installation, engineering solutions will generally be available to mitigate, by means of certain design features, the potential vibratory effects of earthquakes. However, such solutions cannot always be demonstrated to be adequate for mitigating the effects of phenomena of significant permanent ground displacement such as surface faulting, subsidence, ground collapse or fault creep. The objective of this Safety Guide is to provide recommendations and guidance on evaluating seismic hazards at a nuclear installation site and, in particular, on how to determine: (a) the vibratory ground motion hazards, in order to establish the design basis ground motions and other relevant parameters for both new and existing nuclear installations; and (b) the potential for fault displacement and the rate of fault displacement that could affect the feasibility of the site or the safe operation of the installation at

An evaluation of the optimum timing for planting short rotation coppice

Energy Technology Data Exchange (ETDEWEB)

Turnbull, D.J.; Jefferies, R.; Parfitt, R.

2004-07-01

This report summarises the results of a project to determine the optimum timing for planting, evaluate problems due to late planting in the spring, and to study the planting of willows at different times during the autumn. Details are given of the site installation, previous research on the effect of planting date and storage, and assessment of the establishment and biomass productivity and the viability of cuttings in long-term storage. Charts illustrating biomass productivity are presented, and long-term storage of willow cuttings for autumn planting is discussed.

Siting of light-water reactor power plants in the Federal Republic of Germany

International Nuclear Information System (INIS)

Kohler, H.A.G.

1975-01-01

The nuclear power plant site requirements formulated for environment protection in Germany allow nuclear power plants to be built at any site provided these requirements are duly taken into account in preparing and monitoring the site and in the design of the proposed power plant. After a brief discussion of light water reactor power plant sites, prevailing practice in site planning, site selection criteria, licensing procedure and used criteria, rules and guidelines, this paper reports on some considerations taken into account by the expert advisers and by the licensing authorities and future site planning. (orig.) [de

Rocky Flats Plant Site Environmental Report for 1992

Energy Technology Data Exchange (ETDEWEB)

Cirrincione, D.A.; Erdmann, N.L. [eds.

1992-12-31

The Rocky Rats Plant Site Environmental Report provides summary information on the plant`s environmental monitoring programs and the results recorded during 1992. The report contains a compliance summary, results of environmental monitoring and other related programs, a review of environmental remediation activities, information on external gamma radiation dose monitoring, and radiation dose estimates for the surrounding population.

Joint use of laboratory bioassays and field-collected plants to evaluate toxicity and contaminant bioaccumulation

International Nuclear Information System (INIS)

Long, S.P.; Byron, E.R.; Ohlendorf, H.M.

1995-01-01

Soil toxicity tests using lettuce (Latuca saliva) were conducted using soil samples collected as part of ecological risk assessments at two facilities in California. At some sites, terrestrial plants were collected in the field for chemical analysis. Ecological concerns focused on exposures to plants, phytophagous insects, and their secondary consumers, such as birds and small mammals. The toxicity tests were used to assess potential exposures to a variety of site-specific contaminants including organochlorine pesticides, PCBs, PAHs, petroleum hydrocarbons, heavy metals, and other inorganic substances. Site soils were combined with clean control soils to produce toxicity test soil dilutions containing 100%, 75%, 50%, 25%, and 0% site soils. Observations of seed germination and growth were made at day 0, 7, 14, 21 and 28. Toxicity test results were combined with soil chemical analytical results and physical characteristics to establish NOAELs and LOAELs. Bioaccumulation in the lettuce and field-collected plants was evaluated by comparing plant contaminant to soil contaminant concentrations. Allometric equations and sublethal toxicity data were used to predict potential effects on birds and small mammals. Whole-body contaminant concentrations in insects collected on some of the plants in the field were also considered in evaluating the potential for toxicity to insectivorous birds. The study indicated that contaminant uptake was occurring in the field-collected and bioassay plants but not the insects. Site factors in addition to soil contaminant concentration influenced the potential for plant toxicity and bioaccumulation

Volcanic Hazards in Site Evaluation for Nuclear Installations

Energy Technology Data Exchange (ETDEWEB)

NONE

2012-10-15

This publication provides comprehensive and updated guidance for site evaluation in relation to volcanic hazards. It includes recommendations on assessing the volcanic hazards at a nuclear installation site, in order to identify and characterize, in a comprehensive manner, all potentially hazardous phenomena that may be associated with future volcanic events. It describes how some of these volcanic phenomena may affect the acceptability of the selected site, resulting in exclusion of a site or determining the corresponding design basis parameters for the installation. This Safety Guide is applicable to both existing and new sites, and a graded approach is recommended to cater for all types of nuclear installations. Contents: 1. Introduction; 2. Overview of volcanic hazard assessment; 3. General recommendations; 4. Necessary information and investigations (database); 5. Screening of volcanic hazards; 6. Site specific volcanic hazard assessment; 7. Nuclear installations other than nuclear power plants; 8. Monitoring and preparation for response; 9. Management system for volcanic hazard assessment; Annex I: Volcanic hazard scenarios; Annex II: Worldwide sources of information.

Managing Siting Activities for Nuclear Power Plants

International Nuclear Information System (INIS)

2012-01-01

One of the IAEA's statutory objectives is to ''seek to accelerate and enlarge the contribution of atomic energy to peace, health and prosperity throughout the world''. One way this objective is achieved is through the publication of a range of technical series. Two of these are the IAEA Nuclear Energy Series and the IAEA Safety Standards Series. According to Article III.A.6 of the IAEA Statute, the safety standards establish 'standards of safety for protection of health and minimization of danger to life and property.' The safety standards include the Safety Fundamentals, Safety Requirements and Safety Guides. These standards are written primarily in a regulatory style, and are binding on the IAEA for its own programmes. The principal users are the regulatory bodies in Member States and other national authorities. The IAEA Nuclear Energy Series comprises reports designed to encourage and assist R and D on, and application of, nuclear energy for peaceful uses. This includes practical examples to be used by owners and operators of utilities in Member States, implementing organizations, academia, and government officials, among others. This information is presented in guides, reports on technology status and advances, and best practices for peaceful uses of nuclear energy based on inputs from international experts. The IAEA Nuclear Energy Series complements the IAEA Safety Standards Series. The introduction of nuclear power brings new challenges to States - one of them being the selection of appropriates sites. It is a project that needs to begin early, be well managed, and deploy good communications with all stakeholders; including regulators. This is important, not just for those States introducing nuclear power for the first time, but for any State looking to build a new nuclear power plant. The purpose of the siting activities goes beyond choosing a suitable site and acquiring a licence. A large part of the project is about producing and maintaining a validated

Managing Siting Activities for Nuclear Power Plants

Energy Technology Data Exchange (ETDEWEB)

NONE

2012-06-15

One of the IAEA's statutory objectives is to ''seek to accelerate and enlarge the contribution of atomic energy to peace, health and prosperity throughout the world''. One way this objective is achieved is through the publication of a range of technical series. Two of these are the IAEA Nuclear Energy Series and the IAEA Safety Standards Series. According to Article III.A.6 of the IAEA Statute, the safety standards establish 'standards of safety for protection of health and minimization of danger to life and property.' The safety standards include the Safety Fundamentals, Safety Requirements and Safety Guides. These standards are written primarily in a regulatory style, and are binding on the IAEA for its own programmes. The principal users are the regulatory bodies in Member States and other national authorities. The IAEA Nuclear Energy Series comprises reports designed to encourage and assist R and D on, and application of, nuclear energy for peaceful uses. This includes practical examples to be used by owners and operators of utilities in Member States, implementing organizations, academia, and government officials, among others. This information is presented in guides, reports on technology status and advances, and best practices for peaceful uses of nuclear energy based on inputs from international experts. The IAEA Nuclear Energy Series complements the IAEA Safety Standards Series. The introduction of nuclear power brings new challenges to States - one of them being the selection of appropriates sites. It is a project that needs to begin early, be well managed, and deploy good communications with all stakeholders; including regulators. This is important, not just for those States introducing nuclear power for the first time, but for any State looking to build a new nuclear power plant. The purpose of the siting activities goes beyond choosing a suitable site and acquiring a licence. A large part of the project is about producing and maintaining a validated

Site evaluation using measured meteorology data

Energy Technology Data Exchange (ETDEWEB)

Cooper, R. E.; Rusche, B. C. [Savannah River Lab., E.I. du Pont de Nemours and Co., Aiken, South Carolina (United States)

1967-07-01

A key factor in reactor site evaluation is the frequency of occurrence of various dispersion conditions and this relationship to potential off-site doses following a reactor accident. Detailed measurements of the wind speed, wind direction, and temperature at heights up to 1200 ft at the Savannah River Plant form the basis for a comprehensive analysis of the frequency of occurrence of potential off-site doses. A complete set of data was taken about every five minutes, and 107,000 sets (about one year of data) were analyzed. The meteorology data were converted to ordinary dispersion parameters through correlating equations developed at Brookhaven National Laboratory. The results were expressed on curves in dose per unit release of activity vs distance from the reactor with probability of occurrence as a parameter. Separate sets of curves were calculated for releases of noble gas and of halogens and at release heights of 200 ft (a nominal stack height) and of 850 ft (about the height of the tallest power plant stacks). Additional curves were developed to show dose as a function of direction and probability of occurrence. In addition to the dose frequency distribution analyses performed as a function of height of release, direction, and distance; more conventional frequency distributions of wind speed, wind direction, and thermal stability were developed as a function of height. All the analyses were carried out on the IBM 360/65. These results represent the first known analysis utilizing data up to 1200 ft and taken often enough to develop reliable frequency distributions for a short term release. (author)

Evaluation of Visual and Landscape Impacts of Nuclear Power Plants

International Nuclear Information System (INIS)

Algohary, S.A.

2007-01-01

The nuclear power plant is a huge structure, and in terms of both size and function may result in an unacceptable visual conflict in both local and wider environment. Also, it has major implications in terms of physical, social, economic, environmental and impact on people. The environmental impacts include the visual and landscape aspects of these plants. This paper outlines the main general ideas of the architecture aspects of nuclear power plants, nuclear reactors. Also, it discusses the site selection considerations: Finally, it introduces an approach for the evaluation of visual and landscape impacts of nuclear power plants

Site selection for new nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Rizzo, Paul C.; Dubinsky, Melissa; Tastan, Erdem Onur, E-mail: paul.rizzo@rizzoassoc.com, E-mail: melissa.dubinsky@rizzoassoc.com, E-mail: onur.tastan@rizzoassoc.com [RIZZO Associates Inc., Pittsburgh, PA (United States); Miano, Sandra C., E-mail: scm27@psu.edu [Eletrobras Termonuclear S.A. (ELETRONUCLEAR), RJ (Brazil); Pennsylvania State University, Department of Mechanical and Nuclear Engineering, State College, PA (United States)

2015-07-01

The current methodology for selecting the most advantageous site(s) for nuclear power plant (NPP) development is based on the latest evolution of protocols originally established in the 1990's by the Electric Power Research Institute (EPRI) and others for programs in the USA, and more recently by the International Atomic Energy Agency (IAEA), among others. The methodology includes protocols that account for lessons learned from both the Gen III projects and the catastrophic event at Fukushima, Japan. In general, the approach requires consideration of Exclusionary or 'fatal flaw' Criteria first, based on safety as well as significant impact to the environment or human health. Sites must meet all of these Exclusionary Criteria to be considered for NPP development. Next, the remaining sites are evaluated for Avoidance Criteria that affect primarily ease of construction and operations, which allow a ranking of sites best suited for NPP development. Finally, Suitability Criteria are applied to the potential sites to better differentiate between closely ranked sites. Generally, final selection of a Preferred and an Alternate Site will require balancing of factors, expert judgment, and client input, as sites being compared will differ in their scores associated with different Avoidance Criteria and Suitability Criteria. RIZZO Associates (RIZZO) offers in this paper a modification to this methodology for selecting the site for NPP development, which accords to the categories of Exclusionary, Avoidance and Suitability Criteria strict definitions which can be considered as Absolute Factors, Critical Factors, and Economic Factors for a more focused approach to site selection. Absolute Factors include all of the safety-related Exclusionary Criteria. Critical Factors are those that are difficult to overcome unless extraordinary mitigation measures are implemented; they have a significant impact on the ability of the project to be successful and may cause the

Site selection for new nuclear power plants

International Nuclear Information System (INIS)

Rizzo, Paul C.; Dubinsky, Melissa; Tastan, Erdem Onur; Miano, Sandra C.

2015-01-01

The current methodology for selecting the most advantageous site(s) for nuclear power plant (NPP) development is based on the latest evolution of protocols originally established in the 1990's by the Electric Power Research Institute (EPRI) and others for programs in the USA, and more recently by the International Atomic Energy Agency (IAEA), among others. The methodology includes protocols that account for lessons learned from both the Gen III projects and the catastrophic event at Fukushima, Japan. In general, the approach requires consideration of Exclusionary or 'fatal flaw' Criteria first, based on safety as well as significant impact to the environment or human health. Sites must meet all of these Exclusionary Criteria to be considered for NPP development. Next, the remaining sites are evaluated for Avoidance Criteria that affect primarily ease of construction and operations, which allow a ranking of sites best suited for NPP development. Finally, Suitability Criteria are applied to the potential sites to better differentiate between closely ranked sites. Generally, final selection of a Preferred and an Alternate Site will require balancing of factors, expert judgment, and client input, as sites being compared will differ in their scores associated with different Avoidance Criteria and Suitability Criteria. RIZZO Associates (RIZZO) offers in this paper a modification to this methodology for selecting the site for NPP development, which accords to the categories of Exclusionary, Avoidance and Suitability Criteria strict definitions which can be considered as Absolute Factors, Critical Factors, and Economic Factors for a more focused approach to site selection. Absolute Factors include all of the safety-related Exclusionary Criteria. Critical Factors are those that are difficult to overcome unless extraordinary mitigation measures are implemented; they have a significant impact on the ability of the project to be successful and may cause the

Characterization and remediation of a former manufactured gas plant (MGP) disposal site

International Nuclear Information System (INIS)

Murarka, I.P.; Neuhauser, E.F.; Sherman, M.W.; Taylor, B.B.; Mauro, D.M.; Ripp, J.A.; Taylor, T.D.

1993-01-01

From the early 1800s through the late 1940s, the production of gas using coal, coke or oil resulted in generation of large volumes of residues including coal tar, lamp black and wood chips containing cyanides at manufactured gas plant (MGP) sites. Often, these tarry residues were disposed of by burial at or near these plants. In recent years, old MGP sites have come under increased scrutiny from environmental regulators. To address the issues of groundwater contamination and need for clean-up, it is necessary to accurately determine where the tarry materials are now located and how different chemicals released from tars have migrated away from their sources. EPRI research at a coal-tar disposal site in New York has focused on examining and evaluating conventional and innovative methods for sampling and analysis to delineate the nature and extent of subsurface contamination, and to assess the efficacy of remedial actions. This paper presents some of the results of this research and offers recommendations on conducting size investigations as well as selecting appropriate remediation measures

Proposed plan for remedial action at the chemical plant area of the Weldon Spring site

International Nuclear Information System (INIS)

1992-11-01

This proposed plan addresses the management of contaminated material at the chemical plant area of the Weldon Spring site and nearby properties in St. Charles County, Missouri. The site consists of a chemical plant area and a noncontiguous limestone quarry, both of which are radioactively and chemically contaminated as a result of past processing and disposal activities. Explosives were produced at the chemical plant in the 1940s, and uranium and thorium materials were processed in the 1950s and 1960s. Various liquid, sludge, and solid wastes were disposed of at the Chemical plant area and in the quarry during that time. The Weldon Spring site is listed on the National Priorities List (NPL) of the US Environmental Protection Agency (EPA), and the US Department of Energy (DOE) is conducting cleanup activities at the site under its Environmental Restoration and Waste Management Program. The proposed plan is organized as follows: Chapter 2 presents the history and setting of the Weldon Spring site and briefly describes the contaminated material at the chemical plant area. Chapter 3 defines the scope of the remedial action and its role in the Weldon Spring Site Remedial Action Project. Chapter 4 summarizes the risks associated with possible exposures to site contaminants in the absence of remedial action and identifies proposed cleanup levels for soil. Chapter 5 briefly describes the final alternatives considered for the remedial action. Chapter 6 summarizes the evaluation of final alternatives for managing the contaminated material, identifies the currently preferred alternative, and discusses a possible contingency remedy to provide treatment flexibility. Chapter 7 presents the community's role in this action. Chapter 8 is a list of the references cited in this proposed plan

Final report of fugitive and diffuse emissions evaluations at the Hanford Site, CY 1994

International Nuclear Information System (INIS)

Gleckler, B.P.; Schmidt, J.W.

1995-01-01

The objective of this study was to evaluate several of Hanford's major diffuse emission sources and evaluate the effectiveness of monitoring these sources individually versus collectively. The results from this evaluation may also be utilized to demonstrate Westinghouse's compliance status with the applicable air emissions regulations and determine if additional studies and/or evaluations are necessary. Air sampling results from four waste handling and storage facilities were collected for a one week period and analyzed. The following is a list of the selected sampling sites: Plutonium Finishing Plant; 241-BY Tank Farm; 1301-N Trench; 300 Area Trenches and North Ponds. These sites were chosen as being representative of most of the Hanford waste sites, which are known to be diffuse emission sites. The sites were evaluated on the following criteria: physical size, surface contamination levels, geology, vegetation density, surface cover, potential for occupational exposure, and potential for public exposure. The selected sites vary greatly with the selection criteria parameters, and as a result should provide representative data for most of Hanford's waste sites

Geologic CO₂ Sequestration Potential of 42 California Power Plant Sites: A Status Report to WESTCARB

Energy Technology Data Exchange (ETDEWEB)

Myers, Katherine B.L. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Wagoner, J. L. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

2011-06-15

Forty-two California natural gas combined-cycle (NGCC) power plant sites were evaluated for geologic carbon dioxide (CO₂) sequestration potential. The following data were collected in order to gauge the sequestration potential of each power plant site: nearest potential CO₂ sink, proximity to oil or gas fi elds, subsurface geology, surface expression of nearby faults, and subsurface water. The data for each site were compiled into a one-page, standalone profi le to serve as a quick reference for future decision-makers. A subset of these data was compiled into a summary table for easy comparison of all 42 sites. Decision-makers will consider the geologic CO₂ sequestration potential of each power plant in concert with its CO₂ capture potential and will select the most suitable sites for a future carbon capture and storage project. Once the most promising sites are selected, Lawrence Livermore National Laboratory (LLNL) will conduct additional geologic research in order to construct a detailed 3D geologic model for those sites.

Early Site Permit Demonstration Program: Plant parameters envelope report. Volume 1

Energy Technology Data Exchange (ETDEWEB)

1993-03-01

The Early Site Permit (ESP) Demonstration Program is the nuclear industry`s initiative for piloting the early resolution of siting-related issues before the detailed design proceedings of the combined operating license review. The ESP Demonstration Program consists of three phases. The plant parameters envelopes task is part of Phase 1, which addresses the generic review of applicable federal regulations and develops criteria for safety and environmental assessment of potential sites. The plant parameters envelopes identify parameters that characterize the interface between an ALWR design and a potential site, and quantify the interface through values selected from the Utility Requirements Documents, vendor design information, or engineering assessments. When augmented with site-specific information, the plant parameters envelopes provide sufficient information to allow ESPs to be granted based on individual ALWR design information or enveloping design information for the evolutionary, passive, or generic ALWR plants. This document is expected to become a living document when used by future applicants.

Alternative off-site power supply improves nuclear power plant safety

International Nuclear Information System (INIS)

Gjorgiev, Blaže; Volkanovski, Andrija; Kančev, Duško; Čepin, Marko

2014-01-01

Highlights: • Additional power supply for mitigation of the station blackout event in NPP is used. • A hydro power plant is considered as an off-site alternative power supply. • An upgrade of the probabilistic safety assessment from its traditional use is made. • The obtained results show improvement of nuclear power plant safety. - Abstract: A reliable power system is important for safe operation of the nuclear power plants. The station blackout event is of great importance for nuclear power plant safety. This event is caused by the loss of all alternating current power supply to the safety and non-safety buses of the nuclear power plant. In this study an independent electrical connection between a pumped-storage hydro power plant and a nuclear power plant is assumed as a standpoint for safety and reliability analysis. The pumped-storage hydro power plant is considered as an alternative power supply. The connection with conventional accumulation type of hydro power plant is analysed in addition. The objective of this paper is to investigate the improvement of nuclear power plant safety resulting from the consideration of the alternative power supplies. The safety of the nuclear power plant is analysed through the core damage frequency, a risk measure assess by the probabilistic safety assessment. The presented method upgrades the probabilistic safety assessment from its common traditional use in sense that it considers non-plant sited systems. The obtained results show significant decrease of the core damage frequency, indicating improvement of nuclear safety if hydro power plant is introduced as an alternative off-site power source

Evaluation and comparison of high population density sites

International Nuclear Information System (INIS)

Margulies, T.S.

1979-10-01

Consideration of the population distribution surrounding a potential nuclear site generally includes the calculation of population density over a circular area outward to a radial distance of 30 miles from the site. A recently proposed nuclear site Perryman, Maryland challenged the NRC population density guidelines and motivated this project which was performed under the Maryland Power Plant Siting Program. The report provides a comparison of several site population factor indices for comparing relative public safety aspects of alternative nuclear power plant sites. In addition, it is illustrated that use of the reactor safety study (WASH-1400) consequence model as a tool for comparing the relative safety of alternative sites has potential pitfalls

Evaluation of environmental data relating to selected nuclear power plant sites. Kewaunee Nuclear Power Plant site

International Nuclear Information System (INIS)

Murarka, I.P.; Ferrante, J.G.; Policastro, A.J.; Daniels, E.W.

1976-08-01

Environmental monitoring data for the years 1973, 1974 and 1975 pertaining to the Kewaunee Plant, which began operation in mid-1974, were analyzed by qualitative and quantitative methods. The results showed no significant immediate deleterious effects, thus confirming preoperational predictions. Although the plant has not operated long enough to reveal long-term deleterious effects, the present indications do not lead to a prediction that any are developing. The data acquired, method of analysis, and results obtained are presented in detail along with recommendations for improving monitoring techniques

The problem of nuclear power plants site survey and selection

International Nuclear Information System (INIS)

Anh, T.H.; Hung, H.V.; Bui Quoc Thang

1986-01-01

The article presents the main steps of nuclear power plants siting, including the requirements from a nuclear power station onto the site, and the analysis of potential effects of a nuclear power station to the environment. Attentions are called upon the analysis of important factors such as electric transmission losses, cooling water supply, site accessibility, local infrastructure, risks due to man made and natural sources of aggression to the nuclear power plants, population, distribution, hydrological and atmospheric dispersion conditions

Evaluation of surface water treatment and discharge options for the Weldon Spring Site Remedial Action Project

International Nuclear Information System (INIS)

Goyette, M.L.; MacDonell, M.M.

1992-01-01

The US Department of Energy (DOE), under its Environmental Restoration and Waste Management Program, is responsible for conducting response actions at the Weldon Spring site in St. Charles County, Missouri. The site consists of two noncontiguous areas: (1) the chemical plant area, which includes four raffinate pits and two small ponds, and (2) a 3.6-ha (9-acre) quarry located about 6.4 km (4 mi) southwest of the chemical plant area. Both of these areas became chemically and radioactively contaminated as a result of processing and disposal activities that took place from the 1940s through 1960s. The Weldon Spring site, located about 48 km (30 mi) west of St. Louis, is listed on the National Priorities List of the US Environmental Protection Agency. Nitroaromatic explosives were processed by the Army at the chemical plant area during the 1940s, and radioactive materials were processed by DOE's predecessor agency (the Atomic Energy Commission) during the 1950s and 1960s. Overall remediation of the Weldon Spring site is being addressed through the Weldon Spring Site Remedial Action Project, and it consists of several components. One component is the management of radioactively and chemically contaminated surface water impoundments at the chemical plant area -- i.e., the four raffinate pits, Frog Pond, and Ash Pond which was addressed under a separate action and documented in an engineering evaluation/cost analysis report. This report discusses the evaluation of surface water treatment at the Weldon Spring site

Nuclear power plant siting: Hydrogeologic aspects

International Nuclear Information System (INIS)

1984-01-01

This Safety Guide gives guidelines and methods for determining the ground water concentration of radionuclides that could result from postulated releases from nuclear power plants. The Guide gives recommendations on the data to be collected and the investigations to be performed at various stages of nuclear power plant siting in relation to the various aspects of the movement of accidentally released radioactive material through the ground water, the selection of an appropriate mathematical or physical model for the hydrodynamic dispersion even two-phase distribution of the radioactive material and an appropriate monitoring programme

Field evaluation of a horizontal well recirculation system for groundwater treatment: Pilot test at the Clean Test Site Portsmouth Gaseous Diffusion Plant, Piketon, Ohio

International Nuclear Information System (INIS)

Muck, M.T.; Kearl, P.M.; Siegrist, R.L.

1998-01-01

This report presents the results of field testing a horizontal well recirculation system at the Portsmouth Gaseous Diffusion Plant (PORTS). The recirculation system uses a pair of horizontal wells, one for groundwater extraction and treatment and the other for reinjection of treated groundwater, to set up a recirculation flow field. The induced flow field from the injection well to the extraction well establishes a sweeping action for the removal and treatment of groundwater contaminants. The overall purpose of this project is to study treatment of mixed groundwater contaminants that occur in a thin water-bearing zone not easily targeted by traditional vertical wells. The project involves several research elements, including treatment-process evaluation, hydrodynamic flow and transport modeling, pilot testing at an uncontaminated site, and pilot testing at a contaminated site. The results of the pilot test at an uncontaminated site, the Clean Test Site (CTS), are presented in this report

Assessment parameters for coal-fired generation plant site selection

OpenAIRE

Abbas, Ahmad Rosly; Low, K. S.; Ahmad, Ir. Mohd Noh; Chan, J. H.; Sasekumar, A.; Abdul Ghaffar, Fauza; Osman Salleh, Khairulmaini; Raj, John K.; Abdul Yamin, Saad; Wan Aida, Wan Zahari; Phua, Y. T.; Phua, Y. N.; Wong, Y. Y.; Jamaludin, Ir. Mashitah; Jaafar, Shaari

2005-01-01

In order to meet future demand for electricity, Tenaga Nasional Berhad (TNB) is committedto the long-term strategic planning in locating suitable sites for future development of power stations.Site selection is an important process in the early planning stage of any power plant development asit will have significant implications on the capital investment, operational as well as the environmentand socio-economic costs of the power plant.The aim of this presentation is to briefly describe the t...

The Contribution of Palaeoseismology to Seismic Hazard Assessment in Site Evaluation for Nuclear Installations

International Nuclear Information System (INIS)

2015-06-01

IAEA Safety Standards Series No. SSG-9, Seismic Hazards in Site Evaluation for Nuclear Installations, published in 2010, covers all aspects of site evaluation relating to seismic hazards and recommends the use of prehistoric, historical and instrumental earthquake data in seismic hazard assessments. Prehistoric data on earthquakes cover a much longer period than do historical and instrumental data. However, gathering such data is generally difficult in most regions of the world, owing to an absence of human records. Prehistoric data on earthquakes can be obtained through the use of palaeoseismic techniques. This publication describes the current status and practices of palaeoseismology, in order to support Member States in meeting the recommendations of SSG-9 and in establishing the necessary earthquake related database for seismic hazard assessment and reassessment. At a donors’ meeting of the International Seismic Safety Centre Extrabudgetary Project in January 2011, it was suggested to develop detailed guidelines on seismic hazards. Soon after the meeting, the disastrous Great East Japan Earthquake and Tsunami of 11 March 2011 and the consequent accident at the Fukushima Daiichi nuclear power plant occurred. The importance of palaeoseismology for seismic hazard assessment in site evaluation was highlighted by the lessons learned from the Fukushima Daiichi nuclear power plant accident. However, no methodology for performing investigations using palaeoseismic techniques has so far been available in an IAEA publication. The detailed guidelines and practical tools provided here will be of value to nuclear power plant operating organizations, regulatory bodies, vendors, technical support organizations and researchers in the area of seismic hazard assessment in site evaluation for nuclear installations, and the information will be of importance in support of hazard assessments in the future

1000kW on-site PAFC power plant development and demonstration

Energy Technology Data Exchange (ETDEWEB)

Satomi, Tomohide; Koike, Shunichi [Phosphoric Acid Fuel Cell Technology Research Association (PAFC-TRA), Osaka (Japan); Ishikawa, Ryou [New Energy and Industrial Technology Development Organization (NEDO), Tokyo (Japan)

1996-12-31

Phosphoric Acid Fuel Cell Technology Research Association (PAFC-TRA) and New Energy and Industrial Technology Development Organization (NEDO) have been conducting a joint project on development of a 5000kW urban energy center type PAFC power plant (pressurized) and a 1000kW on-site PAFC power plant (non-pressurized). The objective of the technical development of 1000kW on-site PAFC power plant is to realize a medium size power plant with an overall efficiency of over 70% and an electrical efficiency of over 36%, that could be installed in a large building as a cogeneration system. The components and system integration development work and the plant design were performed in 1991 and 1992. Manufacturing of the plant and installation at the test site were completed in 1994. PAC test was carried out in 1994, and generation test was started in January 1995. Demonstration test is scheduled for 1995 and 1996.

A survey of the underground siting of nuclear power plants

International Nuclear Information System (INIS)

Pinto, S.

1979-12-01

The idea of locating nuclear power plants underground is not new, since in the period of time between the late fifties and the early sixties, four small nuclear plants have been built in Europe in rock cavities. Safety has been, in general, the main motivation for such a siting solution. In the last years several factors such as increasing power transmission costs, decreasing number of suitable sites above ground, increased difficulties in obtaining site approval by the licensing authorities, increasing opposition to nuclear power, increasing concern for extreme - but highly improbable - accidents, together with the possibility of utilizing the waste heat and the urban siting concept have renewed the interest for the underground siting as an alternative to surface siting. The author presents a survey of the main studies carried out on the subject of underground siting. (Auth.)

Evaluation of environmental data relating to selected nuclear power plant sites. A synthesis and summary with recommendations

International Nuclear Information System (INIS)

Murarka, I.P.; Policastro, A.J.; Ferrante, J.G.; Daniels, E.W.; Marmer, G.J.

1976-11-01

An analysis of the fuel data gathered during the monitoring programs at seven nuclear power plant sites show no significant ecological impacts. This conclusion is within the constraints of the quality of available data from these sites. Current monitoring programs are, however, not designed to meet the needs for statistical analysis and, consequently, the monitoring data are often ill-suited for modern statistical procedures. Recommendations are proposed for revising monitoring schemes so that more precise conclusions can be made from fewer field measurements

Case study of siting technology for underground nuclear power plant

International Nuclear Information System (INIS)

Hibino, Satoshi; Komada, Hiroya; Honsho, Shizumitsu; Fujiwara, Yoshikazu; Motojima, Mutsumi; Nakagawa, Kameichiro; Nosaki, Takashi

1991-01-01

Underground siting method is one of new feasible siting methods for nuclear power plants. This report presents the results on case studies on underground siting. Two sites of a steeply inclined and plateau like configurations were selected. 'Tunnel type cavern; all underground siting' method was applied for the steeply inclined configuration, and 'shaft type semi-cavern; partial underground siting' method was applied for the plateau like configuration. The following designs were carried out for these two sites as case studies; (1) conceptual designs, (2) geological surveys and rock mechanics tests, (3) stability analysis during cavern excavations, (4) seismic stability analysis of caverns during earthquake, (5) reinforcement designs for caverns, (6) drainage designs. The case studies showed that these two cases were fully feasible, and comparison between two cases revealed that the 'shaft type semi-cavern; partial underground siting' method was more suitable for Japanese islands. As a first step of underground siting, therefore, the authors recommend to construct a nuclear power plant by this method. (author)

Recommended criteria for the evaluation of on-site nuclear power plant emergency exercises

International Nuclear Information System (INIS)

Lafortune, J.F.

1997-01-01

A review of existing Canadian and International emergency exercise evaluation criteria and approaches has been conducted. Based on the results of the review, criteria are proposed for the evaluation of on-site emergency exercises for Canadian nuclear power stations. The proposed criteria are performance-based. They are comprehensive, yet remain adaptable to all stations and accident scenarios. They are primarily aimed at radiological emergency exercises, but are entirely applicable to fire or other conventional exercises. This report also addresses evaluation preparation and methodology. (author). 21 refs., 6 tabs

An Extreme Meteorological Events Analysis For Nuclear Power Plant (NPP) Siting Project at Bangka Island, Indonesia

Science.gov (United States)

Septiadi, Deni; S, Yarianto Sugeng B.; Sriyana; Anzhar, Kurnia; Suntoko, Hadi

2018-03-01

The potential sources of meteorological phenomena in Nuclear Power Plant (NPP) area of interest are identified and the extreme values of the possible resulting hazards associated which such phenomena are evaluated to derive the appropriate design bases for the NPP. The appropriate design bases shall be determined according to the Nuclear Energy Regulatory Agency (Bapeten) applicable regulations, which presently do not indicate quantitative criteria for purposes of determining the design bases for meteorological hazards. These meteorological investigations are also carried out to evaluate the regional and site specific meteorological parameters which affect the transport and dispersion of radioactive effluents on the environment of the region around the NPP site. The meteorological hazards are to be monitored and assessed periodically over the lifetime of the plant to ensure that consistency with the design assumptions is maintained throughout the full lifetime of the facility.

Code on the safety of nuclear power plants: Siting

International Nuclear Information System (INIS)

1988-01-01

This Code provides criteria and procedures that are recommended for safety in nuclear power plant siting. It forms part of the Agency's programme for establishing Codes and Safety Guides relating to land based stationary thermal neutron power plants

Evaluation of dynamic properties, local site effects and design ground motions: recent advances

International Nuclear Information System (INIS)

Sitharam, T.G.; Vipin, K.S.; James, Naveen

2011-01-01

Evidences from past earthquakes clearly shows that the damages due to an earthquake and its severity at a site are controlled mainly by three factors i.e., earthquake source and path characteristics, local geological and geotechnical characteristics, structural design and quality of the construction. Seismic ground response at a site is strongly influenced by local geological and soil conditions. The exact information of the geological, geomorphological and geotechnical data along with seismotectonic details are necessary to evaluate the ground response. The geometry of the subsoil structure, the soil type, the lateral discontinuities and the surface topography will also influence the site response at a particular location. In the case of a nuclear power plant, the details obtained from the site investigation will have multiple objectives: (i) for the effective design of the foundation (ii) assessment of site amplification (iii) for liquefaction potential evaluation. Since the seismic effects on the structure depend fully on the site conditions and assessment of site amplification. The first input required in evaluation of geotechnical aspect of seismic hazard is the rock level peak horizontal acceleration (PHA) values. The surface level acceleration values need to be calculated based on the site conditions and site amplification values. This paper discusses various methods for evaluating the site amplification values, dynamic soil properties, different field and laboratory tests required and various site classification schemes. In addition to these aspects, the evaluation of liquefaction potential of the site is also presented. The paper highlights on the latest testing methods to evaluate dynamic properties (shear modulus and damping ratio) of soils and techniques for estimating local site effects. (author)

Quality assurance in siting of Nuclear Power Plants

International Nuclear Information System (INIS)

2005-03-01

This guide describes the requirements of quality assurance programme (QAP) that need to be implemented at the siting stage, by the organisation having overall responsibility for the nuclear power plant. The scope of the guide covers the quality assurance aspects related to management, performance and assessment activities during siting stage of NPPs

Seismic evaluation of non-seismically designed existing Magnox nuclear power plants

International Nuclear Information System (INIS)

Kunar, R.R.

1984-01-01

The philosophy and method adopted for the seismic assessment of three existing Magnox nuclear stations in the United Kingdom are presented in this paper. The plants were not seismically designed. The particular procedures that were applied were tailored to suit the difficulties of lack of data which is somewhat inevitable for plants designed and built about 25 to 30 years ago. Special procedures included on-site testing with a portable shake table, low vibration testing using a structural dynamics analyser, and on-site inspections. The low vibration testing was most invaluable in detecting differences between 'as-built' conditions and the engineering drawings. From the point of view of economics, this was more effective than conducting full structural surveys to determine the as-built conditions. The testing results also provided confidence in the answers from numerical models. The philosophy adopted for the Magnox reactors in the seismic assessment was to determine what peak ground accelerations the sites can sustain and then evaluate the chances of exceeding the ground accelerations over the remaining lifetime of the plants. The peak ground acceleration for each site was determined on the basis of the criteria of safe shutdown and prevention of significant off-site radiological exposure

Rocky Flats Plant Site Environmental Report for 1992

International Nuclear Information System (INIS)

Cirrincione, D.A.; Erdmann, N.L.

1992-01-01

The Rocky Rats Plant Site Environmental Report provides summary information on the plant's environmental monitoring programs and the results recorded during 1992. The report contains a compliance summary, results of environmental monitoring and other related programs, a review of environmental remediation activities, information on external gamma radiation dose monitoring, and radiation dose estimates for the surrounding population

War protected underground siting of nuclear power plants -a summary

International Nuclear Information System (INIS)

1974-06-01

In connection with studies concerning the need of war protected nuclear power production the technical and economical conditions with war protection of nuclear power plants have been studied within CDL. Comprehensively one have shown that no technical construction obstacles for siting a nuclear power plant underground exist that the additional costs for underground siting with price level mid 1973 are some 175-250 MSwCr (In today's price level 250 MSwCr will probably correspond to some 300 MSwCr per unit) and that the construction time is some one year longer than for an above ground plant. A study ought to examine more closely the consequences of underground siting from a radiological point of view and what demands on that occasion ought to be put on the technical design. (author)

Plan for addressing issues relating to oil shale plant siting

Energy Technology Data Exchange (ETDEWEB)

Noridin, J. S.; Donovan, R.; Trudell, L.; Dean, J.; Blevins, A.; Harrington, L. W.; James, R.; Berdan, G.

1987-09-01

The Western Research Institute plan for addressing oil shale plant siting methodology calls for identifying the available resources such as oil shale, water, topography and transportation, and human resources. Restrictions on development are addressed: land ownership, land use, water rights, environment, socioeconomics, culture, health and safety, and other institutional restrictions. Descriptions of the technologies for development of oil shale resources are included. The impacts of oil shale development on the environment, socioeconomic structure, water availability, and other conditions are discussed. Finally, the Western Research Institute plan proposes to integrate these topics to develop a flow chart for oil shale plant siting. Western Research Institute has (1) identified relative topics for shale oil plant siting, (2) surveyed both published and unpublished information, and (3) identified data gaps and research needs. 910 refs., 3 figs., 30 tabs.

Rocky Flats Plant Site Environmental Report: 1993 Highlights

Energy Technology Data Exchange (ETDEWEB)

1993-12-31

The Rocky Flats Plant Site Environmental Report provides summary information on the plant`s environmental monitoring programs and the results recorded during 1993. The report contains a compliance summary, results of environmental monitoring and other related programs, a review of environmental remediation activities, information on external gamma radiation dose monitoring, and radiation dose estimates for the surrounding population. This section provides an overview of these topics and summarizes more comprehensive discussions found in the main text of this annual report.

Development of plant status display system for on-site educational training system

International Nuclear Information System (INIS)

Yoshimura, Seiichi; Fujimoto, Junzo; Okamoto, Hisatake; Tsunoda, Ryohei; Watanabe, Takao; Masuko, Jiro.

1986-01-01

The purpose of this system is to make easy the comprehension of the facility and dynamics of nuclear power plants. This report describes the tendency and future position of how the educational training system should be, and furthermore describes the experiment. Main results are as follows. 1. The present status and the future tendency of educational training system for nuclear power plant operators. CAI (Computer Assisted Instruction) system has following characteristics. (1) It is easy to introduce plant specific characteristics to the educational training. (2) It is easy to execute the detailed training for the compensation of the full-scale simulator. 2. Plant status display system for on-site educational training system. The fundamental function of the system is as follows. (1) It has 2 CRT displays and voice output devices. (2) It has easy manupulation type of man-machine interface. (3) It has the function for the evaluation of the training results. 3. The effectiveness of this system. The effectiveness evaluation test has been carried out by using this system actually. (1) This system has been proved to be essentially effective and some improvements for the future utilization has been pointed out. (2) It should be faster when the CRT displayes are changed, and it should have the explanation function when the plant transients are displayed. (author)

Assessment of earthquake-induced tsunami hazard at a power plant site

International Nuclear Information System (INIS)

Ghosh, A.K.

2008-01-01

This paper presents a study of the tsunami hazard due to submarine earthquakes at a power plant site on the east coast of India. The paper considers various sources of earthquakes from the tectonic information, and records of past earthquakes and tsunamis. Magnitude-frequency relationship for earthquake occurrence rate and a simplified model for tsunami run-up height as a function of earthquake magnitude and the distance between the source and site have been developed. Finally, considering equal likelihood of generation of earthquakes anywhere on each of the faults, the tsunami hazard has been evaluated and presented as a relationship between tsunami height and its mean recurrence interval (MRI). Probability of exceedence of a certain wave height in a given period of time is also presented. These studies will be helpful in making an estimate of the tsunami-induced flooding potential at the site

Seismic Vulnerability Assessment of Site-Vicinity Infrastructure for Supporting the Accident Management of a Nuclear Power Plant

Directory of Open Access Journals (Sweden)

T. J. Katona

2017-01-01

Full Text Available Nuclear power plants shall be designed to resist the effects of large earthquakes. The design basis earthquake affects large area around the plant site and can cause serious consequences that will affect the logistical support of the emergency actions at the plant, influence the psychological condition of the plant personnel, and determine the workload of the country’s disaster management personnel. In this paper the main qualitative findings of a study are presented that have been performed for the case of a hypothetical 10−4/a probability design basis earthquake for the Paks Nuclear Power Plant, Hungary. The study covers the qualitative assessment of the postearthquake conditions at the settlements around the plant site including quantitative evaluation of the condition of dwellings. The main goal of the recent phase of the study was to identify public utility vulnerabilities that define the outside support conditions of the nuclear power plant accident management. The results of the study can be used for the planning of logistical support of the plant accident management staff. The study also contributes to better understanding of the working conditions of the disaster management services in the region around the nuclear power plant.

Decommissioning strategy and schedule for a multiple reactor nuclear power plant site

Energy Technology Data Exchange (ETDEWEB)

Monteiro, Deiglys Borges; Moreira, Joao M.L.; Maiorino, Jose Rubens, E-mail: deiglys.monteiro@ufabc.edu.br, E-mail: joao.moreira@ufabc.edu.br, E-mail: joserubens.maiorino@ufabc.edu.br [Universidade Federal do ABC (CECS/UFABC), Santo Andre, SP (Brazil). Centro de Engenharia, Modelagem e Ciencias Aplicadas

2015-07-01

The decommissioning is an important part of every Nuclear Power Plant life cycle gaining importance when there are more than one plant at the same site due to interactions that can arise from the operational ones and a decommissioning plant. In order to prevent undesirable problems, a suitable strategy and a very rigorous schedule should implemented and carried. In this way, decommissioning tasks such as fully decontamination and dismantling of activated and contaminated systems, rooms and structures could be delayed, posing as an interesting option to multiple reactor sites. The present work aims to purpose a strategy and a schedule for the decommissioning of a multiple reactor site highlighting the benefits of delay operational tasks and constructs some auxiliary services in the site during the stand by period of the shutdown plants. As a case study, will be presented a three-reactor site which the decommissioning process actually is in planning stage and that should start in the next decade. (author)

Decommissioning strategy and schedule for a multiple reactor nuclear power plant site

International Nuclear Information System (INIS)

Monteiro, Deiglys Borges; Moreira, Joao M.L.; Maiorino, Jose Rubens

2015-01-01

The decommissioning is an important part of every Nuclear Power Plant life cycle gaining importance when there are more than one plant at the same site due to interactions that can arise from the operational ones and a decommissioning plant. In order to prevent undesirable problems, a suitable strategy and a very rigorous schedule should implemented and carried. In this way, decommissioning tasks such as fully decontamination and dismantling of activated and contaminated systems, rooms and structures could be delayed, posing as an interesting option to multiple reactor sites. The present work aims to purpose a strategy and a schedule for the decommissioning of a multiple reactor site highlighting the benefits of delay operational tasks and constructs some auxiliary services in the site during the stand by period of the shutdown plants. As a case study, will be presented a three-reactor site which the decommissioning process actually is in planning stage and that should start in the next decade. (author)

Pinellas Plant FY1990 site specific implementation plan

International Nuclear Information System (INIS)

Klein, R.D.

1990-02-01

This Site Specific Implementation Plan describes the Corrective Action, Environmental Restoration, and Waste Management activities to be performed at the Pinellas Plant in FY1990 (October 1, 1989 to September 30, 1989). These FY1990 activities are described in the Pinellas Plant FY1991--95 Five-Year Plan. The information used to prepare this plan reflects the best estimate of the project scope, schedules, regulatory, and funding requirements at the time of plan preparation. The Environmental Restoration/Waste Management Five-Year Plan is a dynamic document and will be modified each year; the Site Specific Implementation Plan will, in turn, be modified each year to reflect new findings, information, and knowledge of the various projects. 4 figs., 11 tabs

Sludge stabilization at the Plutonium Finishing Plant, Hanford Site, Richland, Washington

International Nuclear Information System (INIS)

1994-10-01

This Environmental Assessment evaluates the proposed action to operate two laboratory-size muffle furnaces in glovebox HC-21C, located in the Plutonium Finishing Plant (PFP), Hanford Site, Richland, Washington. The muffle furnaces would be used to stabilize chemically reactive sludges that contain approximately 25 kilograms (55 pounds) of plutonium by heating to approximately 500 to 1000 degrees C (900 to 1800 degrees F). The resulting stable powder, mostly plutonium oxide with impurities, would be stored in the PFP vaults. The presence of chemically reactive plutonium-bearing sludges in the process gloveboxes poses a risk to workers from radiation exposure and limits the availability of storage space for future plant cleanup. Therefore, there is a need to stabilize the material into a form suitable for long-term storage. This proposed action would be an interim action, which would take place prior to completion of an Environmental Impact Statement for the PFP which would evaluate stabilization of all plutonium-bearing materials and cleanout of the facility. However, only 10 percent of the total quantity of plutonium in reactive materials is in the sludges, so this action will not limit the choice of reasonable alternatives or prejudice the Record of Decision of the Plutonium Finishing Plant Environmental Impact Statement

Preliminary Evaluation of Removing Used Nuclear Fuel from Shutdown Sites

Energy Technology Data Exchange (ETDEWEB)

Maheras, Steven J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Best, Ralph E. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Ross, Steven B. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Buxton, Kenneth A. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); England, Jeffery L. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); McConnell, Paul E. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Massaro, Lawrence M. [Fermi Research Alliance (FRA), Batavia, IL (United States); Jensen, Philip J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

2016-09-30

A preliminary evaluation of removing spent nuclear fuel (SNF) from 13 shutdown nuclear power plant sites was performed. At these shutdown sites the nuclear power reactors have been permanently shut down and the sites have been decommissioned or are undergoing decommissioning. The shutdown sites were Maine Yankee, Yankee Rowe, Connecticut Yankee, Humboldt Bay, Big Rock Point, Rancho Seco, Trojan, La Crosse, Zion, Crystal River, Kewaunee, San Onofre, and Vermont Yankee. The evaluation was divided into four components: Characterization of the SNF and greater-than-Class C low-level radioactive waste (GTCC waste) inventory A description of the on-site infrastructure at the shutdown sites An evaluation of the near-site transportation infrastructure and transportation experience at the shutdown sites An evaluation of the actions necessary to prepare for and remove SNF and GTCC waste. The primary sources for the inventory of SNF and GTCC waste were the U.S. Department of Energy (DOE) spent nuclear fuel inventory database, industry publications such as StoreFUEL, and government sources such as the U.S. Nuclear Regulatory Commission. The primary sources for information on the conditions of on-site infrastructure and near-site transportation infrastructure and experience included information collected during site visits, information provided by managers at the shutdown sites, Facility Interface Data Sheets compiled for DOE in 2005, Services Planning Documents prepared for DOE in 1993 and 1994, industry publications such as Radwaste Solutions, and Google Earth. State staff, State Regional Group representatives, a Tribal representative, and a Federal Railroad Administration representative have participated in nine of the shutdown site visits. Every shutdown site was found to have at least one off-site transportation mode option for removing its SNF and GTCC waste; some have multiple options. Experience removing large components during reactor decommissioning provided an

Performance evaluation of effluent treatment plant for automobile industry

Energy Technology Data Exchange (ETDEWEB)

Ansari, Farid [Department of Applied Science and Humanities, PDM College of Engineering, Bahadurgarh (Haryana) (India); Pandey, Yashwant K. [School of Energy and Environmental Studies, Devi Ahilya Vishwavidyalaya, Indore (India); Kumar, P.; Pandey, Priyanka [Department of Environmental Science, Post Graduate College Ghazipur (IN

2013-07-01

The automobile industry’s wastewater not only contains high levels of suspended and total solids such as oil, grease, dyestuff, chromium, phosphate in washing products, and coloring, at various stages of manufacturing but also, a significant amount of dissolved organics, resulting in high BOD or COD loads. The study reveals the performance, evaluation and operational aspects of effluent treatment plant and its treatability, rather than the contamination status of the real property. The Results revealed that the treated effluent shows most of the parameters are within permissible limits of Central Pollution Control Board (CPCB), India and based on the site visits, discussion with operation peoples, evaluation of process design, treatment system, existing effluent discharge, results of sample analyzed and found that effluent treatment plant of automobile industry are under performance satisfactory.

Screening criteria of volcanic hazards aspect in the NPP site evaluation

International Nuclear Information System (INIS)

Nur Siwhan

2013-01-01

Studies have been conducted on the completeness of regulation in Indonesia particularly on volcanic hazards aspects in the evaluation of nuclear power plant site. Volcanic hazard aspect needed to identify potential external hazards that may endanger the safety of the operation of nuclear power plants. There are four stages for evaluating volcanic hazards, which are initial assessment, characterization sources of volcanic activity in the future, screening volcanic hazards and assessment of capable volcanic hazards. This paper discuss the third stage of the general evaluation which is the screening procedure of volcanic hazards. BAPETEN Chairman Regulation No. 2 Year of 2008 has only one screening criteria for missile volcanic phenomena, so it required screening criteria for other hazard phenomena that are pyroclastic flow density; lava flows; avalanche debris materials; lava; opening hole new eruptions, volcano missile; tsunamis; ground deformation; and hydrothermal system and ground water anomaly. (author)

Characterization recommendations for waste sites at the Savannah River Plant

International Nuclear Information System (INIS)

Carlton, W.H.; Gordon, D.E.; Johnson, W.F.; Kaback, D.S.; Looney, B.B.; Nichols, R.L.; Shedrow, C.B.

1987-11-01

One hundred and sixty six disposal facilities that received or may have received waste materials resulting from operations at the Savannah River Plant (SRP) have been identified. These waste range from innocuous solid and liquid materials (e.g., wood piles) to process effluents that contain hazardous and/or radioactive constituents. The waste sites have been grouped into 45 categories according the the type of waste materials they received. Waste sites are located with SRP coordinates, a local Department of Energy (DOE) grid system whose grid north is 36 degrees 22 minutes west of true north. DOE policy is to close all waste sites at SRP in a manner consistent with protecting human health and environment and complying with applicable environmental regulations (DOE 1984). A uniform, explicit characterization program for SRP waste sites will provide a sound technical basis for developing closure plans. Several elements are summarized in the following individual sections including (1) a review of the history, geohydrology, and available characterization data for each waste site and (2) recommendations for additional characterization necessary to prepare a reasonable closure plan. Many waste sites have been fully characterized, while others have not been investigated at all. The approach used in this report is to evaluate available groundwater quality and site history data. For example, groundwater data are compared to review criteria to help determine what additional information is required. The review criteria are based on regulatory and DOE guidelines for acceptable concentrations of constituents in groundwater and soil

Assessment of social values in thermal plant siting

International Nuclear Information System (INIS)

Anon.

1976-01-01

The objective of the project is to develop a method for combining social values with techno-economic data for better decision making in thermal nuclear power plant siting. Quantified technical impact data which is socially weighted will allow for the optimal choice of site/design alternatives. In this phase, a study of community leadership in energy/environment issues was conducted in a town familiar with a (nuclear) thermal power plant. Secondly, a linear composite analysis of the measurement problems associated with combining diverse scales of impacts was completed. Third, a revision of the social values instrument used in a previous phase of the study was initiated. Finally, liaison activities with utilities were undertaken. Quantification of three of the technical impact factors is currently underway

The potential environmental impacts and the siting of proposed nuclear power plants in China

International Nuclear Information System (INIS)

Shi Zhongqi

1986-01-01

This paper reviews briefly the methodology of assessing environmental impacts from the nuclear power plants and analyses the potential radiological impacts on the environment from proposed nuclear power plants in China. Preliminary studies show that the environmental impacts of the effluents of routine release from PWRs to the proposed sites are extremely small, even if nuclear power plants are constructed either on the Bohai Sea shore with a narrow mouth or in the densely populated regions of Sunan. Thus, the suitability of sites depends mainly on the acceptability of possible exposure to the residents following postulated accidental release of radioactive materials. The paper also discusses relations between the nuclear plant siting and population distribution around the site and compares the distribution of the proposed sites in China with that of other countries sites in according to China actual situation, it is reasonable to adopt a prudent policy that the first series of nuclear power plants in China should be built in relatively low population areas

Proposed plan for remedial action for the Groundwater Operable Unit at the Chemical Plant Area of the Weldon Spring Site, Weldon Spring, Missouri

International Nuclear Information System (INIS)

1999-01-01

This Proposed Plan addresses the remediation of groundwater contamination at the chemical plant area of the Weldon Spring site in Weldon Spring, Missouri. The site is located approximately 48 km (30 mi) west of St. Louis in St. Charles County . Remedial activities at the site will be conducted in accordance with the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA). The U.S. Department of Energy (DOE), in conjunction with the U.S. Department of the Army (DA), conducted a joint remedial investigation/feasibility study (RI/FS) to allow for a comprehensive evaluation of groundwater conditions at the Weldon Spring chemical plant area and the Weldon Spring ordnance works area, which is an Army site adjacent to the chemical plant area. Consistent with DOE policy, National Environmental Policy Act (NEPA) values have been incorporated into the CERCLA process. That is, the analysis conducted and presented in the RVFS reports included an evaluation of environmental impacts that is comparable to that performed under NEPA. This Proposed Plan summarizes information about chemical plant area groundwater that is presented in the following documents: (1) The Remedial Investigation (RI), which presents information on the nature and extent of contamination; (2) The Baseline Risk Assessment (BRA), which evaluates impacts to human health and the environment that could occur if no cleanup action of the groundwater were taken (DOE and DA 1997a); and (3) The Feasibility Study (FS) and the Supplemental FS, which develop and evaluate remedial action alternatives for groundwater remediation

Toward a regional power plant siting method: AEC-Maryland regional siting factors study, FY 1974 progress report

International Nuclear Information System (INIS)

Yaffee, S.L.; Miller, C.A.

1974-11-01

The ''AEC-Maryland Regional Siting Factors Study'' examines the process of siting in a regional context. It is developing an analysis method to delineate candidate areas for siting of several power plant technology packages, including both fossil-fueled and nuclear options. Tools that are being used include simulation modeling, economic and demographic forecasting, spatial analysis, and computer graphics and numerical manipulation. The approach will describe the trade-offs incurred if a power plant is located in one candidate area rather than in another. In FY 1974, a suitability analysis method was developed which uses engineering and environmental parameters to define a level of environmental cost incurred if a segment of land is used to site a specific technology package. (U.S.)

Thermal power plants in the Oslofjord district - Recipient evaluations

International Nuclear Information System (INIS)

Boehle, B.; Danielssen, D.; Tveite, S.; Haugen, I.; Nilsen, G.; Audunson, T.; Rye, H.; Thendrup, A.

1975-11-01

The results presented in a series of reports from the three institutes concerning the physical characteristics of the waters in the vicinoty of five possible sites for thermal (including nuclear) power plants in the Oslofjord district, and the spreading and effects of thermal effluents on the biological state and resources of these waters, are summarised, and an evaluation of the relative suitability of these sites is made. The sites are ranked as follows:- 1. Naverfjorden or, 2. Langangsfjorden - Saga, with effluent release to the Naverfjord region in both cases; 3. Vardeaasen; 4. Hurum; 5; Brenntangen. The possible intake - outlet arrangements are ranked as follows:-1. Deep intake - surface outlet, 2. Deep intake - deep outlet, or surface intake - surface outlet, 3. Surface intake - deep outlet. (JIW)

Native Plant Uptake Model for Radioactive Waste Disposal Areas at the Nevada Test Site

Energy Technology Data Exchange (ETDEWEB)

BROWN,THERESA J.; WIRTH,SHARON

1999-09-01

This report defines and defends the basic framework, methodology, and associated input parameters for modeling plant uptake of radionuclides for use in Performance Assessment (PA) activities of Radioactive Waste Management Sites (RWMS) at the Nevada Test Site (NTS). PAs are used to help determine whether waste disposal configurations meet applicable regulatory standards for the protection of human health, the environment, or both. Plants adapted to the arid climate of the NTS are able to rapidly capture infiltrating moisture. In addition to capturing soil moisture, plant roots absorb nutrients, minerals, and heavy metals, transporting them within the plant to the above-ground biomass. In this fashion, plant uptake affects the movement of radionuclides. The plant uptake model presented reflects rooting characteristics important to plant uptake, biomass turnover rates, and the ability of plants to uptake radionuclides from the soil. Parameters are provided for modeling plant uptake and estimating surface contaminant flux due to plant uptake under both current and potential future climate conditions with increased effective soil moisture. The term ''effective moisture'' is used throughout this report to indicate the soil moisture that is available to plants and is intended to be inclusive of all the variables that control soil moisture at a site (e.g., precipitation, temperature, soil texture, and soil chemistry). Effective moisture is a concept used to simplify a number of complex, interrelated soil processes for which there are too little data to model actual plant available moisture. The PA simulates both the flux of radionuclides across the land surface and the potential dose to humans from that flux. Surface flux is modeled here as the amount of soil contamination that is transferred from the soil by roots and incorporated into aboveground biomass. Movement of contaminants to the surface is the only transport mechanism evaluated with the model

Native Plant Uptake Model for Radioactive Waste Disposal Areas at the Nevada Test Site

International Nuclear Information System (INIS)

Brown, Theresa J.; Wirth, Sharon

1999-01-01

This report defines and defends the basic framework, methodology, and associated input parameters for modeling plant uptake of radionuclides for use in Performance Assessment (PA) activities of Radioactive Waste Management Sites (RWMS) at the Nevada Test Site (NTS). PAs are used to help determine whether waste disposal configurations meet applicable regulatory standards for the protection of human health, the environment, or both. Plants adapted to the arid climate of the NTS are able to rapidly capture infiltrating moisture. In addition to capturing soil moisture, plant roots absorb nutrients, minerals, and heavy metals, transporting them within the plant to the above-ground biomass. In this fashion, plant uptake affects the movement of radionuclides. The plant uptake model presented reflects rooting characteristics important to plant uptake, biomass turnover rates, and the ability of plants to uptake radionuclides from the soil. Parameters are provided for modeling plant uptake and estimating surface contaminant flux due to plant uptake under both current and potential future climate conditions with increased effective soil moisture. The term ''effective moisture'' is used throughout this report to indicate the soil moisture that is available to plants and is intended to be inclusive of all the variables that control soil moisture at a site (e.g., precipitation, temperature, soil texture, and soil chemistry). Effective moisture is a concept used to simplify a number of complex, interrelated soil processes for which there are too little data to model actual plant available moisture. The PA simulates both the flux of radionuclides across the land surface and the potential dose to humans from that flux. Surface flux is modeled here as the amount of soil contamination that is transferred from the soil by roots and incorporated into aboveground biomass. Movement of contaminants to the surface is the only transport mechanism evaluated with the model presented here

Numerical Simulation of Groundwater Flow at Kori Nuclear Power Plant Site

International Nuclear Information System (INIS)

Sohn, Wook; Sohn, Soon Whan; Chon, Chul Min; Kim, Kue Youn

2010-01-01

Recently, the understanding of hydrogeological characteristics of nuclear power sites is getting more importance with increasing public concerns over the environment since such understanding is essential for an environmentally friendly operation of plants. For such understanding, the prediction of groundwater flow pattern onsite plays the most critical role since it is the most dynamic of the factors to be considered. In this study, the groundwater flow at the Kori Plant 1 site has been simulated numerically with aim of providing fundamental information needed for improving the understanding of the hydrogeological characteristics of the site

Environmental Insights from Siting New Nuclear Power Plants in the United States

International Nuclear Information System (INIS)

Kugler, Andrew J.

2013-01-01

This described the Part 52 combined licence review process, under which a design certification and an early site permit can come together to allow a limited work authorization to be issued for pre-construction work while the combined Construction and Operation Licence (COL) application is being considered by the regulator. The regulatory then performs ITAAC (Inspection, Test, Analysis, Acceptance Criteria) to verify that the as-build plant conforms to what was licensed. The Siting Safety Review that is performed under the COL process considers factors such as geology, surface faulting, seismology, geotechnical engineering, hydrology, flooding and groundwater. For an existing site, this involves updating the hazard evaluation from the original one. Dose consequence calculations are performed for both design basis accidents and severe accidents. Experience with siting has shown that all applicants deviate from the guidance, that it is difficult to compare existing sites with new sites, that water supply is a bigger issue now than it was for existing reactors and that site selection can come down to a choice 'among the best', rather than the 'best possible'. Consideration of alternative sites is a big part of the process; the U.S.NRC can reject a primary site if an alternative site appears to be more appropriate, though it cannot force an applicant to select a secondary site

SSC [Superconducting Super Collider] site evaluations

International Nuclear Information System (INIS)

1988-11-01

With this report, the SSC Site Task Force forwards to the Director, Office of Energy Research, US Department of Energy (DOE), its evaluation of the technical criteria and life-cycle costs for the proposed SSC sites judged to be the best qualified. The criteria against which each site was evaluated are those set forth in the Invitation for Site Proposals for the Superconducting Super Collider (DOE/ER-0315) (Invitation) which was prepared by the Task Force and issued in April 1987. The methodology followed by the Task Force in this report and in all other phases of the proposal evaluation has been consistent with the SSC site selection process approved by DOE's Energy System Acquisition Advisory Board (ESAAB). The goal of the site selection process is to identify a site that will permit the highest level of research productivity and overall effectiveness of the SSC at a reasonable cost of construction and operation and with minimial impact on the environment. The Task Force acknowledges that all seven sites are, indeed, highly qualified locations for the construction and operation of the SSC on the basis of technical and cost considerations. In performing its evaluation, which is presented in this paper, the Task Force took an in-depth look at each site on the basis of site visits and extensive technical analyses. A consensus rating for each technical evaluation criterion and subcriterion was developed for each site

Portsmouth Gaseous Diffusion Plant annual site environmental report for 1993

Energy Technology Data Exchange (ETDEWEB)

Horak, C.M. [ed.

1994-11-01

This calendar year (CY) 1993 annual report on environmental monitoring of the US Department of Energy`s (DOE`s) Portsmouth Gaseous Diffusion Plant (Portsmouth) and its environs consists of three separate documents: a summary pamphlet for the general public; a more detail discussion and of compliance status, data, and environmental impacts (this document); and a volume of detailed data that is available on request. The objectives of this report are to report compliance status during 1993; provide information about the plant site and plant operations; report 1993 monitoring data for the installation and its environs that may have been affected by operations on the plant site; document information on input and assumptions used in calculations; provide trend analyses (where appropriate) to indicate increases and decreases in environmental impact, and provide general information on quality assurance for the environmental monitoring program.

Portsmouth Gaseous Diffusion Plant annual site environmental report for 1993

International Nuclear Information System (INIS)

Horak, C.M.

1994-11-01

This calendar year (CY) 1993 annual report on environmental monitoring of the US Department of Energy's (DOE's) Portsmouth Gaseous Diffusion Plant (Portsmouth) and its environs consists of three separate documents: a summary pamphlet for the general public; a more detail discussion and of compliance status, data, and environmental impacts (this document); and a volume of detailed data that is available on request. The objectives of this report are to report compliance status during 1993; provide information about the plant site and plant operations; report 1993 monitoring data for the installation and its environs that may have been affected by operations on the plant site; document information on input and assumptions used in calculations; provide trend analyses (where appropriate) to indicate increases and decreases in environmental impact, and provide general information on quality assurance for the environmental monitoring program

Cytochrome c1 exhibits two binding sites for cytochrome c in plants.

Science.gov (United States)

Moreno-Beltrán, Blas; Díaz-Quintana, Antonio; González-Arzola, Katiuska; Velázquez-Campoy, Adrián; De la Rosa, Miguel A; Díaz-Moreno, Irene

2014-10-01

In plants, channeling of cytochrome c molecules between complexes III and IV has been purported to shuttle electrons within the supercomplexes instead of carrying electrons by random diffusion across the intermembrane bulk phase. However, the mode plant cytochrome c behaves inside a supercomplex such as the respirasome, formed by complexes I, III and IV, remains obscure from a structural point of view. Here, we report ab-initio Brownian dynamics calculations and nuclear magnetic resonance-driven docking computations showing two binding sites for plant cytochrome c at the head soluble domain of plant cytochrome c1, namely a non-productive (or distal) site with a long heme-to-heme distance and a functional (or proximal) site with the two heme groups close enough as to allow electron transfer. As inferred from isothermal titration calorimetry experiments, the two binding sites exhibit different equilibrium dissociation constants, for both reduced and oxidized species, that are all within the micromolar range, thus revealing the transient nature of such a respiratory complex. Although the docking of cytochrome c at the distal site occurs at the interface between cytochrome c1 and the Rieske subunit, it is fully compatible with the complex III structure. In our model, the extra distal site in complex III could indeed facilitate the functional cytochrome c channeling towards complex IV by building a "floating boat bridge" of cytochrome c molecules (between complexes III and IV) in plant respirasome. Copyright © 2014 Elsevier B.V. All rights reserved.

Evaluation Of The Exclusion And Low Population Areas Around A Nuclear Power Plant

International Nuclear Information System (INIS)

Tawfik, F.S.

2011-01-01

Being adjacent to the nuclear power plant (NPP) the exclusion area (EA) is the area of greatest importance. It essentially defines a buffer zone where the public has no access. It helps to define the fenced plant area, the site area and the public area. Also, the low population area is the area immediately surrounding the exclusion area near a licensed reactor in terms of public safety and the ability of residents to get away from the plant in an emergency. This study clarifies their significance and reviews the international approach on them. Assuming the nuclear power plant site at the north coast of Egypt, the exclusion area and low population area are determined according to CFR (2002). In this method, a maximum possible amount of radioactivity release (called a source term) should be assumed. The boiling water reactor (BWR) with a power 1000 MW was used to carry the calculation and assuming a severe loss of coolant accident with meltdown of reactor. The site specific data have been collected, investigated and processed. The effect of the degree of atmospheric stability and building width of the plant were examined. The proceeding factors that control the determination of exclusion area and low population area should be taken into consideration in the site evaluation stage and design basis of NPP to set a minimum distances for them

Insights from the U.S. department of Energy plant safety evaluation program of VVER and RBMK reactors

International Nuclear Information System (INIS)

Petri, M.C.; Binder, J.L.; Pasedag, W.F.

2001-01-01

Throughout the years 1990 the U.S. Department of Energy has worked build capability in countries of the former Soviet Union to assess the safety of their VVER and RBMK reactors. Through this Plant Safety Evaluation Program, deterministic and probabilistic analyses have been used to provide a documented plant risk profile to support safe plant operation and to set priorities for safety upgrades. Work has been sponsored at thirteen nuclear power plant sites in eight countries. The Plant Safety Evaluation Program has resulted in immediate and long-term safety benefits for the Soviet-designed nuclear plants. (author)

Geotechnical evaluation of the proposed WIPP site in southeast New Mexico

International Nuclear Information System (INIS)

Weart, W.D.

1978-10-01

The Department of Energy is proposing to demonstrate the acceptability of geologic disposal of radioactive waste by locating a Waste Isolation Pilot Plant (WIPP) in the salt beds 26 miles east of Carlsbad, New Mexico. The WIPP will serve as a permanent repository for defense generated transuranic contaminated waste and will also be used as a facility in which experiments and demonstrations with all radioactive waste types can be conducted. The present area being proposed for the WIPP is the second such location in the Delaware Basin for which new site data have been developed; the first site proved geologically unacceptable. Ecologic and socioeconomic aspects have been investigated and extensive geophysical, geological and hydrologic studies have been conducted to allow an evaluation of site acceptability. Geotechnical aspects of site characterization are examined. These studies are now sufficiently complete that the site can be recommended for further development of the WIPP

Remedial investigation for the chemical plant area of the Weldon Spring Site

International Nuclear Information System (INIS)

1992-11-01

The US Department of Energy (DOE) is responsible for management of the Weldon Spring Site Remedial Action Project (WSSRAP) under its Environmental Restoration and Waste Management Program. Major goals include eliminating potential public and environmental hazards due to site contamination and releasing the property for alternate uses to the maximum extent practicable. The purpose of the remedial investigation described in this report was to determine the extent of contamination associated with the portion of the Weldon Spring site known as the chemical plant and raffinate pit area. The DOE has assumed responsibility for investigating and remediating all on-site soil contamination and off-site soil which is radiologically contaminated as a result of uranium and thorium processing operations. The DOE has also assumed the responsibility for radiologically contaminated groundwater on and off site. The Weldon Spring site remedial investigation also involved the evaluation of the sources, nature and extent, and environmental fate and transport of contaminants to provide a basis for defining the risks that the contaminants may pose to human health and the environment. Data are included in this report to support the screening of remedial technologies and to permit the development and detailed analysis of alternatives for remedial action at the site during the feasibility study process

Survival and growth of restored Piedmont riparian forests as affected by site preparation, planting stock, and planting aids

Science.gov (United States)

Chelsea M. Curtis; W. Michael Aust; John R. Seiler; Brian D. Strahm

2015-01-01

Forest mitigation sites may have poor survival and growth of planted trees due to poor drainage, compacted soils, and lack of microtopography. The effects of five replications of five forestry mechanical site preparation techniques (Flat, Rip, Bed, Pit, and Mound), four regeneration sources (Direct seed, Bare root, Tubelings, and Gallon), and three planting aids (None...

Blasting jobs on the building site of the Temelin nuclear power plant

International Nuclear Information System (INIS)

Voda, J.; Podel, R.

1984-01-01

The problems are discussed of the preparation and implementation on the Temelin nuclear power plant building site of blasting, the volume of drilling and the choice of the drill hammer - all based on experience gained during the construction of the Mochovce nuclear power plant. The amount of explosives used on the Temelin site will be 1400 t. The use of mechanical charging may shorten the preparation of the site by 20 to 30%. Explosive emulsion slurries are being developed from home raw materials whose application will reduce the volume of drilling by 15%. The method of controlled breaking secures adequate quality of peripheral walls and bottom chink but special explosives will have to be used. Seismic effects are discussed of blasting on dwellings, agricultural and industrial buildings in the vicinity of the site, on-site buildings, underground mains and special structures of the nuclear power plant. (E.S.)

A risk evaluation model using on-site meteorological data

International Nuclear Information System (INIS)

Kang, C.S.

1979-01-01

A model is considered in order to evaluate the potential risk from a nuclear facility directly combining the on site meteorological data. The model is utilized to evaluate the environmental consequences from the routine releases during normal plant operation as well as following postulated accidental releases. The doses to individual and risks to the population-at-large are also analyzed in conjunction with design of rad-waste management and safety systems. It is observed that the conventional analysis, which is done in two separate unaffiliated phases of releases and atmospheric dispersion tends to result in unnecessary over-design of the systems because of high resultant doses calculated by multiplication of two extreme values. (author)

Safety criteria for siting a nuclear power plant

International Nuclear Information System (INIS)

2001-01-01

The guide sets forth requirements for safety of the population and the environment in nuclear power plant siting. It also sets out the general basis for procedures employed by other competent authorities when they issue regulations or grant licences. On request STUK (Radiation and Nuclear Safety Authority of Finland) issues case-specific statements about matters relating to planning and about other matters relating to land use in the environment of nuclear power plants

Preliminary Evaluation of Removing Used Nuclear Fuel from Shutdown Sites

Energy Technology Data Exchange (ETDEWEB)

Maheras, Steven J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Best, Ralph E. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Ross, Steven B. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Buxton, Kenneth A. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); England, Jeffery L. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); McConnell, Paul E. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Massaro, Lawrence M. [Federal Railroad Administration (FRA) (United States); Jensen, Philip J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

2014-10-01

This report presents a preliminary evaluation of removing used nuclear fuel (UNF) from 12 shutdown nuclear power plant sites. At these shutdown sites the nuclear power reactors have been permanently shut down and the sites have been decommissioned or are undergoing decommissioning. The shutdown sites are Maine Yankee, Yankee Rowe, Connecticut Yankee, Humboldt Bay, Big Rock Point, Rancho Seco, Trojan, La Crosse, Zion, Crystal River, Kewaunee, and San Onofre. The evaluation was divided into four components: characterization of the UNF and greater-than-Class C low-level radioactive waste (GTCC waste) inventory; a description of the on-site infrastructure and conditions relevant to transportation of UNF and GTCC waste; an evaluation of the near-site transportation infrastructure and experience relevant to shipping transportation casks containing UNF and GTCC waste, including identification of gaps in information; and, an evaluation of the actions necessary to prepare for and remove UNF and GTCC waste. The primary sources for the inventory of UNF and GTCC waste are the U.S. Department of Energy (DOE) RW-859 used nuclear fuel inventory database, industry sources such as StoreFUEL and SpentFUEL, and government sources such as the U.S. Nuclear Regulatory Commission. The primary sources for information on the conditions of site and near-site transportation infrastructure and experience included observations and information collected during visits to the Maine Yankee, Yankee Rowe, Connecticut Yankee, Humboldt Bay, Big Rock Point, Rancho Seco, Trojan, La Crosse, and Zion sites; information provided by managers at the shutdown sites; Facility Interface Data Sheets compiled for DOE in 2005; Services Planning Documents prepared for DOE in 1993 and 1994; industry publications such as Radwaste Solutions; and Google Earth. State and Regional Group representatives, a Tribal representative, and a Federal Railroad Administration representative participated in six of the shutdown site

Utility survey on nuclear power plant siting and nuclear energy centers

International Nuclear Information System (INIS)

Cope, D.F.; Bauman, H.F.

1977-01-01

Most of the large U.S. utilities were surveyed by telephone and mail on questions concerning nuclear power plant siting and nuclear energy centers (NECs). The main purpose of the survey was for guidance of ERDA's NEC program. The questions covered the following topics: availability of sites; impact of environmental and other restraints; plans for development of multi-unit sites; interest in NEC development; interest in including fuel-cycle facilities in NECs; and opinions on the roles desired for the state and Federal governments in power plant siting. The main conclusion of the survey was that, while many utilities were considering multiple-unit sites of 2 to 5 units, none were planning larger energy centers at the present time. However, several expressed interest in NECs as a long-range future development

An assessment and evaluation for recycle/reuse of contaminated process and metallurgical equipment at the DOE Rocky Flats Plant Site -- Building 865

International Nuclear Information System (INIS)

1993-08-01

An economic analysis of the potential advantages of alternatives for recycling and reusing equipment now stored in Building 865 at the Rocky Flats Plant (RFP) in Colorado has been conducted. The inventory considered in this analysis consists primarily of metallurgical and process equipment used before January 1992, during development and production of nuclear weapons components at the site. The economic analysis consists of a thorough building inventory and cost comparisons for four equipment dispositions alternatives. The first is a baseline option of disposal at a Low Level Waste (LLW) landfill. The three alternatives investigated are metal recycling, reuse with the government sector, and release for unrestricted use. This report provides item-by-item estimates of value, disposal cost, and decontamination cost. The economic evaluation methods documented here, the simple cost comparisons presented, and the data provided as a supplement, should provide a foundation for D ampersand D decisions for Building 865, as well as for similar D ampersand D tasks at RFP and at other sites

The part played by applied geology in nuclear power plant site studies

International Nuclear Information System (INIS)

Giafferi, J.L.

1994-01-01

Site-related geological problems are one of the constraints affecting the environment of nuclear power plants. The natural features (soil and subsoil) at the nuclear power plant site affect numerous factors in the design, construction and operation of the civil engineering structures. The site geological criteria are not solely restricted to the soil as a static support for the structures. Earth tremors in France are of moderate intensity but the likelihood of their occurrence must nevertheless be taken into account for each site. Studies must concern the geological and seismic features of the region as well as the soil and subsoil configurations and composition in the immediate vicinity of the site in order to determine the physical characteristics of the earthquakes so that the safety of the plant can be guaranteed; in many cases, water tables have also to be taken into consideration. Geologic survey techniques are discussed. 13 figs., 7 refs

The Choice of Sites for the First Nuclear Power Plants in Brazil

International Nuclear Information System (INIS)

Cintra do Prado, L.

1966-01-01

In selecting the sites for nuclear power plants a decision has to be taken as to (1) which area of the country is best suited for the purpose - e.g. the area of Recife, Rio or Sao Paulo, etc. - given the trend in energy requirements and the availability of resources, and (2) where to site the plant or plants within that area. In this paper I shall concentrate on the first of these problems and shall be concerned with assessing the merits and demerits of installing nuclear power plants in certain regions of Brazil which seem particularly well suited for the purpose

Rocky Flats Plant Site Environmental Report: 1993 Highlights

International Nuclear Information System (INIS)

1993-01-01

The Rocky Flats Plant Site Environmental Report provides summary information on the plant's environmental monitoring programs and the results recorded during 1993. The report contains a compliance summary, results of environmental monitoring and other related programs, a review of environmental remediation activities, information on external gamma radiation dose monitoring, and radiation dose estimates for the surrounding population. This section provides an overview of these topics and summarizes more comprehensive discussions found in the main text of this annual report

Economic evaluation of heat extraction from nuclear power plants - a criterion for deciding their building order

International Nuclear Information System (INIS)

Navratil, J.

1987-01-01

Heat extraction from nuclear power plants is an important element in the current concept of supplying the population and industries with heat. Economic evaluation of the extraction is one of the factors of the total economic assessment of potential sites for nuclear power plant construction which can contribute to decision making on the priorities of construction. The methodological approach to the assessment of economic contribution of heat extraction from 2x1000 MW nuclear power plant is exemplified using three such sites on the Czechoslovak territory, viz., Opatovice (eastern Bohemia), Blahutovice (northern Moravia), and Kecerovce (eastern Slovakia). The so-called annual converted cost was used as a suitable quantity completely reflecting all significant economic effects of heat extraction. It is shown that the fuel component of the power plant costs is the decisive factor for the amount of the annual converted cost in respect to heat supply and thus also the economic priority of the construction sites of nuclear power plants. (Z.M.). 3 tabs., 3 refs

Selection of sites for nuclear power plants in The Netherlands. Pt. A

International Nuclear Information System (INIS)

1985-01-01

In this report a policy proposal is presented concerning the selection of location sites for new nuclear power plants in the Netherlands. Firstly it is investigated which of the 29 already selected location sites are not to be taken into further account because of obvious obstructions (close vicinity of a big city etc.). The remaining sites are judged on the base of local population magnitude. The sites that pass the last criteria are relatively compared from a large number of viewpoints. To round off the selection procedure the government will explain why they consider the finally selected sites to be suitable for location of new nuclear power plants. Steps are indicated to prevent the decrease of planologic suitability of the selected location sites. (Auth.)

Power from waste. [Power plant at landfill site

Energy Technology Data Exchange (ETDEWEB)

Anon,

1991-01-01

Base Load Systems Ltd, a company in the United Kingdom, has just commissioned a power plant in Leicestershire which uses waste gases from a landfill site. The gases power two specially modified turbo charged engine and generator packages. The plant will use approximately 100 cu meters of landfill gas per hour and is expected to feed 1.5MW of electrical power into the supply network of East Midlands Electricity. Once the landfill site has been completely filled and capped with clay, it is estimated that the electrical power output will be 4 MW. At present, since their are no customers for heat in the vicinity, 100 KW of the electricity produced are used to run fans to dissipate the 2.5 MW of waste heat. Base load is also involved elsewhere in combined heat and power projects. (UK).

ESPSD, Nuclear Power Plant Siting Database

International Nuclear Information System (INIS)

Slezak, S.

2001-01-01

1 - Description of program or function: This database is a repository of comprehensive licensing and technical reviews of siting regulatory processes and acceptance criteria for advanced light water reactor (ALWR) nuclear power plants. The program is designed to be used by applicants for an early site permit or combined construction permit/operating license (10CFRR522), Sub-parts A and C) as input for the development of the application. The database is a complete, menu-driven, self-contained package that can search and sort the supplied data by topic, keyword, or other input. The software is designed for operation on IBM compatible computers with DOS. 2 - Method of solution: The database is an R:BASE Runtime program with all the necessary database files included

Early site review report for the Sundesert site, San Diego Gas and Electric Company. Project No. 558

International Nuclear Information System (INIS)

1977-01-01

The purpose of the report is to present the Nuclear Regulatory Commission's evaluation of several of the matters relating to the suitability of the Sundesert site near Blythe, California, on which the San Diego Gas and Electric Company proposes to build the Sundesert Nuclear Plant, Units 1 and 2. The report summarizes the results of the technical evaluation of the suitability of the proposed Sundesert site for a nuclear plant and delineates the scope of the technical matters considered in evaluating the suitability of the site

An Evaluation System for Checking the Status of I and C Systems in Nuclear Power Plants

International Nuclear Information System (INIS)

JinWoo, Hyun; Hak-Yeong, Chung; ChanHo, Sung

2006-01-01

I and C upgrade has been hot issue around the world as progresses of degradation, aging and obsolescence have been getting worse with the continual I and C system operation, it is very difficult to develop I and C evaluation system for the real application to nuclear power plants due to complexity or reliability aspects of the methodology. Thus, to improve these problems related to evaluation and application of I and C systems, we have been developing an evaluation system which embarks an objective evaluation methodology and works on internet for convenience. This Evaluation system has been established based on the evaluation factors including system importance, performance, maintenance, aging, economic efficiency and the continuance of equipment supply, and each evaluation factor has some questionnaires which are composed of questions requiring quantitative and qualitative answers. The applied evaluation algorithm consists of scoring process among evaluation factors and weighting factor allocation process. The Evaluation system has a structure based on web environment. With this system, staffs from plant sites can directly conduct the evaluation of each I and C system status of the plant, survey of results, survey of upgrade information, and upgrade/maintenance plan. Also head office utilizes this system for the survey of the evaluation results, upgrade or maintenance plan of each site and especially acquires some useful information for making finance plans. (authors)

Problems in Siting Nuclear Power Plants in Japan and Efforts to Solve Them

Energy Technology Data Exchange (ETDEWEB)

Inouye, T. [Ministry of International Trade and Industry, Tokyo (Japan)

1967-09-15

The rapidly growing demand for energy in Japan will require a total capacity of 30 to 40 thousand MW(e) in nuclear power by 1985. Materialization of this development programme must naturally be supported by securing the requisite sites for the nuclear power plants. The following factors make siting of nuclear power plants more difficult in Japan than in any other country: a small, densely populated territory with little level land, that is already completely utilized for agricultural and/or industrial purposes; small rivers and an active marine-product industry developed along most of the seacoasts, both of which create difficult cooling-water problems; frequent earthquakes; and the fear of possible radioactivity, which prevails in the only nation in the world to have suffered from the atomic bomb. There are at present four nuclear power plants in operation or under construction in Japan with a total capacity of about 1.3 thousand MW(e). However, the plants in these construction programmes have been sited on the basis of taking the easiest course available although there were several possible solutions to choose from. It is pointed out here that the long-range nuclear power development programme will call for a fundamental solution to enable siting a large number of power plants under the adverse conditions in Japan. Accordingly, a study was made, which included quantitative analyses of reactor siting factors and suggested measures for solving the siting problems. The analyses were based on nuclear power plant sites assumed to be located on the seacoast and characterized by low-population density, desirable geology and favourable topography. It was assumed that seacoast siting was more economical than inland siting. Although the study was made by a general survey using maps, it was shown that approximately 10% of the total coastline areas would be eligible for reactor siting, but most of these areas in this case are located in the northern part of Japan, far from

The knowledge-based off-site emergency response system for a nuclear power plant

International Nuclear Information System (INIS)

Ho, L.W.; Loa, W.W.; Wang, C.L.

1987-01-01

A knowledge-based expert system for a nuclear power plant off-site emergency response system is described. The system incorporates the knowledge about the nuclear power plant behaviours, site environment and site geographic factors, etc. The system is developed using Chinshan nuclear power station of Taipower Company, Taiwan, ROC as a representative model. The objectives of developing this system are to provide an automated intelligent system with functions of accident simulation, prediction and with learning capabilities to supplement the actions of the emergency planners and accident managers in order to protect the plant personnel and the surrounding population, and prevent or mitigate property damages resulting from the plant accident. The system is capable of providing local and national authorities with rapid retrieval data from the site characteristics and accident progression. The system can also provide the framework for allocation of available resources and can handle the uncertainties in data and models

Dose assessments in nuclear power plant siting

International Nuclear Information System (INIS)

1988-03-01

This document is mainly intended to provide information on dose estimations and assessments for the purpose of nuclear power plant (NPP) siting. It is not aimed at giving radiation protection guidance, criteria or procedures to be applied during the process of NPP siting nor even to provide recommendations on this subject matter. The document may however be of help for implementing some of the Nuclear Safety Standards (NUSS) documents on siting. The document was prepared before April 26, 1986, when a severe accident at the Unit 4 of Chernobyl NPP in the USSR had occurred. It should be emphasized that this document does not bridge the gap which exists in the NUSS programme as far as radiation protection guidance for the specific case of siting of NPP is concerned. The Agency will continue to work on this subject with the aim to prepare a safety series document on radiation protection requirements for NPP siting. This document could serve as a working document for this purpose. Refs, figs and tabs

Role of satellite and geophysical data for evaluation of site for nuclear power plants - a case study from Rajasthan, India

International Nuclear Information System (INIS)

Chaturvedi, A.K.; Ramesh Babu, V.; Srivastava, P.K.; Sunil, T.C.

2014-01-01

Remote sensing imageries and seismotectonic maps were studied in the light of recently published regional gravity data jointly by NGRI, OIL, GSI and SOl (2006) for accessing the structural fabric of the area to locate suitable site for nuclear power plant. Entire analysis of the data sets has been carried out in Geographical Information Systems (GIS) environment. The study area, Rawatbhata falls well within the Vindhyan Basin bounded by the towns Bundi in the North, Chittaurgarh in the West, Jhalwar in the Southeast and Kota in the Northeast. Interpretation of the arcuate shaped gravity low in the southeast reveals the probable extension of Hindoli Group of Rocks below the Vidhyans and Traps. The selected location is sitting on the gravity high. A gravity gradient of 5 mGal is observed within the 10km buffer zone which is marked in yellow on all the maps. Earlier workers interpreted the thickness of the Vindhyan sediments as 6-7km, based on the deep seismic and gravity surveys, conducted along the Kunjer-Nagaur transect. Study of the seismotectonic maps published by GSI doesn't indicate any seismic activity over the decades. NE-SW trending neotectonic faults and few thermal springs are noticed far away from the study area around 100 km NW of Great Boundary Fault (GBF). Numbers of NE-SW, NW-SE trending major and minor lineaments/faults are present in the region. However, analysis of the geophysical data sets doesn't reflect any such lineaments/faults within 25 km radius. Integrated study of the area helped in evaluating the existing nuclear power plant site. (author)

Evaluation of methods for seismic analysis of nuclear fuel reprocessing plants, part 1

International Nuclear Information System (INIS)

Tokarz, F.J.; Murray, R.C.; Arthur, D.F.; Feng, W.W.; Wight, L.H.; Zaslawsky, M.

1975-01-01

Currently, no guidelines exist for choosing methods of structural analysis to evaluate the seismic hazard of nuclear fuel reprocessing plants. This study examines available methods and their applicability to fuel reprocessing plant structures. The results of this study should provide a basis for establishing guidelines recommending methods of seismic analysis for evaluating future fuel reprocessing plants. The approach taken is: (1) to identify critical plant structures and place them in four categories (structures at or near grade; deeply embedded structures; fully buried structures; equipment/vessels/attachments/piping), (2) to select a representative structure in each of the first three categories and perform static and dynamic analysis on each, and (3) to evaluate and recommend method(s) of analysis for structures within each category. The Barnwell Nuclear Fuel Plant is selected as representative of future commercial reprocessing plants. The effect of site characteristics on the structural response is also examined. The response spectra method of analysis combined with the finite element model for each category is recommended. For structures founded near or at grade, the lumped mass model could also be used. If a time history response is required, a time-history analysis is necessary. (U.S.)

Selection of sites for nuclear power plants in The Netherlands. Pt. C

International Nuclear Information System (INIS)

1986-01-01

This advice is concerned with the question where possible new nuclear power plants can at best be sited in the Netherlands. Safety risks of power plants are considered (sourceterm analysis, meteorologic aspects). A site analysis is presented on the base of criteria like population density, possible emergency provisions, contamination of agricultural areas etc. Reports of several committees are included. (Auth.)

Independent verification in operations at nuclear power plants: Summaries of site visits

International Nuclear Information System (INIS)

Donderi, D.C.; Smiley, A.; Ostry, D.J.; Moray, N.P.

1995-09-01

A critical review of approaches to independent verification in operations used in nuclear power plant quality assurance programs in other countries was conducted and are detailed in volume 1. This paper is a compilation of the visits to nuclear power plant sites to study independent verification in operations at sites in Canada, USA, Japan, United Kingdom, France and Germany. 3 tabs., 22 figs

Evaluation of environmental data relating to selected nuclear power plant sites. The Zion Nuclear Power Station site

International Nuclear Information System (INIS)

Murarka, I.P.; Policastro, A.; Daniels, E.; Ferrante, J.; Vaslow, F.

1976-11-01

Environmental monitoring data for the years 1972 through 1975 pertaining to the Zion Station, which began commercial operation in 1974, were analyzed by the most practical qualitative and quantitative methods. Thermal plume, water chemistry and aquatic biota data were evaluated and the results are presented. The results showed no significant immediate deleterious effects, thus confirming preoperational predictions. Although the plant has not operated long enough to reveal long-term deleterious effects, the present indications do not lead to a concerned prediction that any are developing. The data utilized, the methods of analysis, and the results obtained are presented in detail, along with recommendations for improving monitoring techniques

RNA polyadenylation sites on the genomes of microorganisms, animals, and plants.

Directory of Open Access Journals (Sweden)

Xiu-Qing Li

Full Text Available Pre-messenger RNA (mRNA 3'-end cleavage and subsequent polyadenylation strongly regulate gene expression. In comparison with the upstream or downstream motifs, relatively little is known about the feature differences of polyadenylation [poly(A] sites among major kingdoms. We suspect that the precise poly(A sites are very selective, and we therefore mapped mRNA poly(A sites on complete and nearly complete genomes using mRNA sequences available in the National Center for Biotechnology Information (NCBI Nucleotide database. In this paper, we describe the mRNA nucleotide [i.e., the poly(A tail attachment position] that is directly in attachment with the poly(A tail and the pre-mRNA nucleotide [i.e., the poly(A tail starting position] that corresponds to the first adenosine of the poly(A tail in the 29 most-mapped species (2 fungi, 2 protists, 18 animals, and 7 plants. The most representative pre-mRNA dinucleotides covering these two positions were UA, CA, and GA in 17, 10, and 2 of the species, respectively. The pre-mRNA nucleotide at the poly(A tail starting position was typically an adenosine [i.e., A-type poly(A sites], sometimes a uridine, and occasionally a cytidine or guanosine. The order was U>C>G at the attachment position but A>>U>C≥G at the starting position. However, in comparison with the mRNA nucleotide composition (base composition, the poly(A tail attachment position selected C over U in plants and both C and G over U in animals, in both A-type and non-A-type poly(A sites. Animals, dicot plants, and monocot plants had clear differences in C/G ratios at the poly(A tail attachment position of the non-A-type poly(A sites. This study of poly(A site evolution indicated that the two positions within poly(A sites had distinct nucleotide compositions and were different among kingdoms.

Issues at manufactured gas plant sites

International Nuclear Information System (INIS)

Menzie, C.A.; Unites, D.F.; Nakles, D.

1991-01-01

Gas, manufactured from coal or oil was used to light and heat homes, industries, and streets of this country from the mid-1800s to the late 1940s or early 1950s. The era, with its associated gas lights, faded with the development of natural gas supplies and direct use of other fossil fuels. Today, Manufactured Gas Plant (MGP) sites are part of our history. Most of the MGPs were operated at a time when the state of the environmental sciences was much less sophisticated and the environmental regulations were much less stringent or nonexistent. While there was an awareness of potential environmental problems then the concerns were more qualitative (e.g., odor, color) and resulted in minimal treatment of process residuals. Inasmuch as there may be over a thousand MGP sites in the United States, it also became clear that utility research institutes such as the Gas Research Institute (GRI) and the Electric Power Research Institute (EPRI) should address key research and management issues related to site investigation, risk assessment, and site remediation. Information gained from these research initiatives would serve the industry as a whole, as well as other groups involved in the assessment of MGP sites. This paper provides and overview of these programs and identifies how additional information can be obtained

Evaluation and monitoring of an household waste incineration plant in Paris area

International Nuclear Information System (INIS)

Person, A.; Le Moullec, Y.; Gilibert, E.

1995-01-01

Urban population is more and more concerned by air quality and waste disposal. In Paris Area, municipal waste are incinerated in three large plants all equipped with gas cleaning systems, except one that will be equipped in June 1995. It appeared interesting to characterize and evaluate the impact of this incinerator on ambient air quality in an area where other sources interfere. An sampling campaign was set up on six sites of AIRPARIF (ile de France Air Quality Monitoring Network). Nitrogen oxides. Sulphur dioxide and black smokes are measured in continuously. Other pollutants, considered more specific of waste incineration plants were analysed on a 24 h-sampling basis (heavy metals, hydrochloride acid, Chlorides). The first results seem to show some trends. Regarding usual pollutants, it appears downwind sites present higher average level that upwind sites. For hydrochloric acid, 24 h. averages are higher when the site was frequently downwind during the day. The size of the data set is small for heavy metals, however it seems that an impact can be detected for Cd and Zn. (author)

Modeling groundwater flow at the chemical plant area of the Weldon Spring Site

International Nuclear Information System (INIS)

Durham, L.A.

1992-10-01

Groundwater flow in the shallow unconfined aquifer at the chemical plant area of the Weldon Spring site, St. Charles County, Missouri, was modeled with the Coupled Fluid, Energy, and Solute Transport (CFEST) groundwater flow and contaminant transport computer code. The modeling was performed in support of a hydrogeological characterization effort that is part of the remedial investigation/feasibility study-environmental impact statement process being carried out by the US Department of Energy at the site. This report presents the results of model development and calibration. In the calibration procedure, the range of field-measured hydrogeological parameters was tested to obtain the best match between model-predicted and measured groundwater elevations. After calibration, the model was used to evaluate whether the presence of an on-site disposal cell would impact the ability to remediate contaminated groundwater beneath the cell. The results of the numerical modeling, which were based on an evaluation of steady-state groundwater flow velocity plots, indicated that groundwater would flow beneath the disposal cell along natural gradients. The presence of a disposal cell would not significantly affect remediation capability for groundwater contamination

Remediation System Evaluation, McCormick and Baxter Superfund SiteRemediation System Evaluation, McCormick and Baxter Superfund Site

Science.gov (United States)

The McCormick and Baxter Creosoting Company, Portland Plant, Superfund Site is located adjacent tothe Willamette River in Portland, Oregon and addresses contamination of soil, groundwater, and riversediments stemming from creosoting operations...

Evaluation of tolerance to soils contaminated with diesel oil in plant species with bioremediation potential

International Nuclear Information System (INIS)

Petenello, Maria Cristina; Feldman, Susana Raquel.

2012-01-01

Soils contaminated with hydrocarbons or their derivate can be remediated by different methods. Many of them use live organisms such as plants that are able to mineralize these compounds, turning them into more simple molecules, similar to natural molecules. When the use of plants is decided, it is important to employ native plants because they are already adapted to the particular ecological conditions of the site. The response of spartina argentinensis, paspalum atratum, paspalum guenoarun and melilotus albus to the presence of diesel oil was evaluated considering seed germination, plant emergence and biomass production of plants growing on soils experimentally contaminated with different concentrations of diesel oil (1 and 2 %). Although all the parameters evaluated showed the negative impact of the presence of diesel-oil, the plants continued growing; therefore they can be considered useful management options for soil phytoremediation.

Performance evaluation of the technical capabilities of DOE sites for disposal of mixed low-level waste: Volume 3, Site evaluations

Energy Technology Data Exchange (ETDEWEB)

Waters, R.D.; Gruebel, M.M. [eds.

1996-03-01

A team of analysts designed and conducted a performance evaluation to estimate the technical capabilities of fifteen Department of Energy sites for disposal of mixed low-level waste (i.e., waste that contains both low-level radioactive materials and hazardous constituents). Volume 1 summarizes the process for selecting the fifteen sites, the methodology used in the evaluation, and the conclusions derived from the evaluation. Volume 2 provides details about the site-selection process, the performance-evaluation methodology, and the overall results of the analysis. Volume 3 contains detailed evaluations of the fifteen sites and discussion of the results for each site.

Performance evaluation of the technical capabilities of DOE sites for disposal of mixed low-level waste: Volume 3, Site evaluations

International Nuclear Information System (INIS)

Waters, R.D.; Gruebel, M.M.

1996-03-01

A team of analysts designed and conducted a performance evaluation to estimate the technical capabilities of fifteen Department of Energy sites for disposal of mixed low-level waste (i.e., waste that contains both low-level radioactive materials and hazardous constituents). Volume 1 summarizes the process for selecting the fifteen sites, the methodology used in the evaluation, and the conclusions derived from the evaluation. Volume 2 provides details about the site-selection process, the performance-evaluation methodology, and the overall results of the analysis. Volume 3 contains detailed evaluations of the fifteen sites and discussion of the results for each site

Regulatory requirements for nuclear power plant site selection in Malaysia-a review.

Science.gov (United States)

Basri, N A; Hashim, S; Ramli, A T; Bradley, D A; Hamzah, K

2016-12-01

Malaysia has initiated a range of pre-project activities in preparation for its planned nuclear power programme. Clearly one of the first steps is the selection of sites that are deemed suitable for the construction and operation of a nuclear power plant. Here we outline the Malaysian regulatory requirements for nuclear power plant site selection, emphasizing details of the selection procedures and site characteristics needed, with a clear focus on radiation safety and radiation protection in respect of the site surroundings. The Malaysia Atomic Energy Licensing Board (AELB) site selection guidelines are in accord with those provided in International Atomic Energy Agency (IAEA) and United Stated Nuclear Regulatory Commission (USNRC) documents. To enhance the suitability criteria during selection, as well as to assist in the final decision making process, possible assessments using the site selection characteristics and information are proposed.

Dechlorane Plus (DP) in air and plants at an electronic waste (e-waste) site in South China

Energy Technology Data Exchange (ETDEWEB)

Chen Shejun [State Key Laboratory of Organic Geochemistry, Guangzhou Institute of Geochemistry, Chinese Academy of Sciences, Guangzhou 510640 (China); Tian Mi; Wang Jing; Shi Tian [State Key Laboratory of Organic Geochemistry, Guangzhou Institute of Geochemistry, Chinese Academy of Sciences, Guangzhou 510640 (China); Graduate School, Chinese Academy of Sciences, Beijing 100049 (China); Luo Yong [Guangdong Forestry Survey and Planning Institute, Guangzhou 510520 (China); Luo Xiaojun [State Key Laboratory of Organic Geochemistry, Guangzhou Institute of Geochemistry, Chinese Academy of Sciences, Guangzhou 510640 (China); Mai Bixian, E-mail: nancymai@gig.ac.cn [State Key Laboratory of Organic Geochemistry, Guangzhou Institute of Geochemistry, Chinese Academy of Sciences, Guangzhou 510640 (China)

2011-05-15

Air and foliage samples (Eucalyptus spp. and Pinus massoniana Lamb.) were collected from e-waste and reference sites in South China and analyzed for Dechlorane Plus (DP) and two dechlorinated DPs. DP concentrations in the air were 13.1-1794 pg/m{sup 3} for the e-waste site and 0.47-35.7 pg/m{sup 3} for the reference site, suggesting the recycling of e-waste is an important source of DP to the environment. Plant DP, with concentrations of 0.45-51.9 ng/g dry weight at the e-waste site and 0.09-2.46 ng/g at the reference site, exhibited temporal patterns similar to the air DP except for pine needle at the reference site. The air-plant exchange of DP could be described with the two-compartment model. Anti-Cl{sub 11} DP was measured in most air and plant samples from the e-waste site. The ratios of anti-Cl{sub 11} DP to anti-DP in the air and plants may indicate the preferential uptake of dechlorinated DP by plant compared with DP. - Highlights: > Dechlorane Plus was widely present in the air and plants in South China. > Temporal patterns of the plant DP could be described with the two-compartment model. > Plant uptake can efficiently reduce air DP concentration at the reference site. > Anti-Cl{sub 11} DP was measured in most air and plant samples from the e-waste site. - E-waste recycling in South China results in wide occurrence of DP in the air and plant.

A COUNTY-LEVEL MODEL OF MANUFACTURING PLANT RECRUITMENT WITH IMPROVED INDUSTRIAL SITE QUALITY MEASUREMENT

OpenAIRE

Kriesel, Warren; McNamara, Kevin T.

1991-01-01

Empirical analysis of manufacturing plant location requires the use of a single industrial site quality measure. Under hedonic price theory, the price of industrial sites can be explained by their quality characteristics. The estimated site price is included with ten other location factors in an ordered, categorical logit model of plant attraction to Georgia counties. The results inform public decision-makers of the relative impact of site location factors and how changes in location factors ...

Nuclear power plant attempts in Turkey and the first licensed site

International Nuclear Information System (INIS)

Bektur, Y.; Bezdegumeli, U.

2004-01-01

In this paper, detailed information regarding Turkey's past attempts for the construction of a nuclear power plant (NPP) and site survey studies conducted for this plant is given. Also, some important characteristics of the first licensed site, namely Akkuyu, are summarized. There were four attempts made for the construction of an NPP in the past. However, all of them failed due to technical, economical and/or some other reasons. Akkuyu site has been selected among around 25 candidate sites for the reasons that bulky materials can be transported there by sea; it is located near the major electricity demand centers; soil-structure interaction and slab stability are suitable for the construction of an NPP; its surrounding is one of the most sparsely populated areas of Turkey; and it is seismically the most stable region in earthquake-prone Turkey, e.g. Turkish Electricity Authority (TEK) was granted a site license for the Akkuyu in 1976. (author)

Establishment and Evaluation of Decommissioning Plant Inventory DB and Waste Quantity

International Nuclear Information System (INIS)

Oh, Jae Yong; Moon, Sang-Rae; Yun, Taesik; Kim, Hee-Geun; Sung, Nak-Hoon; Jung, Seung Hyuk

2016-01-01

Korea Hydro and Nuclear Power (KHNP) made a decision for permanent shutdown of Kori-1 and has progressed the strategy determination and R and D for the decommissioning of Kori-1. Decommissioning waste, Structure, System and Components (SSCs) is one of the most important elements. Decommissioning waste quantity is calculated based on Plant Inventory Database (PI DB) with activation and contamination data. Due to the largest portion of waste management and disposal in decommissioning, it is necessary to exactly evaluate waste quantity (applying the regulation, guideline and site-specific characterization) for economic feasibility. In this paper, construction of PI DB and evaluation of waste quantity for Optimized Pressurized Reactor (OPR-1000) are mainly described. Decommissioning waste quantities evaluated are going to be applied to calculation of the project cost. In fact, Ministry of Trade, Industry and Energy (MOTIE) in Korea expected the decommissioning waste quantity in a range of 14,500-18,850 drums, and predicted appropriate liability for decommissioning fund by using waste quantity. The result of this study is also computed by the range of 14,500-18,850 drums. Since there is no site-specific data for the NPP site, this evaluation is the preliminary analysis

Establishment and Evaluation of Decommissioning Plant Inventory DB and Waste Quantity

Energy Technology Data Exchange (ETDEWEB)

Oh, Jae Yong; Moon, Sang-Rae; Yun, Taesik; Kim, Hee-Geun [KHNP CRI, Daejeon (Korea, Republic of); Sung, Nak-Hoon; Jung, Seung Hyuk [KONES Corp., Seoul (Korea, Republic of)

2016-10-15

Korea Hydro and Nuclear Power (KHNP) made a decision for permanent shutdown of Kori-1 and has progressed the strategy determination and R and D for the decommissioning of Kori-1. Decommissioning waste, Structure, System and Components (SSCs) is one of the most important elements. Decommissioning waste quantity is calculated based on Plant Inventory Database (PI DB) with activation and contamination data. Due to the largest portion of waste management and disposal in decommissioning, it is necessary to exactly evaluate waste quantity (applying the regulation, guideline and site-specific characterization) for economic feasibility. In this paper, construction of PI DB and evaluation of waste quantity for Optimized Pressurized Reactor (OPR-1000) are mainly described. Decommissioning waste quantities evaluated are going to be applied to calculation of the project cost. In fact, Ministry of Trade, Industry and Energy (MOTIE) in Korea expected the decommissioning waste quantity in a range of 14,500-18,850 drums, and predicted appropriate liability for decommissioning fund by using waste quantity. The result of this study is also computed by the range of 14,500-18,850 drums. Since there is no site-specific data for the NPP site, this evaluation is the preliminary analysis.

Case study of manufactured gas plant site remediations using thermal desorption

Energy Technology Data Exchange (ETDEWEB)

Vogel, R.G.; Hayes, T.; Slimon, K.F.; Unites, D. [Southern California Gas Company, Los Angeles, CA (United States)

1995-12-31

Southern California Gas Company (SoCal Gas) has recently remediated five of its former manufactured gas plant (MGP) sites using on-site and off-site thermal desorption. This technology has proven effective in the treatment of PAH-contaminated soils with widely variable concentrations. At two of the five sites, MGP-contaminated materials were excavated and thermally treated on site. At the other sites, MGP-contaminated materials were excavated and transported directly to an off-site thermal desorber. Much of the production was of oil-gas, giving lampblack contamination, but some coal tar was also present.

Reassessment of selected factors affecting siting of Nuclear Power Plants

Energy Technology Data Exchange (ETDEWEB)

Davis, R.E.; Hanson, A.L.; Mubayi, V.; Nourbakhsh, H.P.

1997-02-01

Brookhaven National Laboratory has performed a series of probabilistic consequence assessment calculations for nuclear reactor siting. This study takes into account recent insights into severe accident source terms and examines consequences in a risk based format consistent with the quantitative health objectives (QHOs) of the NRC`s Safety Goal Policy. Simplified severe accident source terms developed in this study are based on the risk insights of NUREG-1150. The results of the study indicate that both the quantity of radioactivity released in a severe accident as well as the likelihood of a release are lower than those predicted in earlier studies. The accident risks using the simplified source terms are examined at a series of generic plant sites, that vary in population distribution, meteorological conditions, and exclusion area boundary distances. Sensitivity calculations are performed to evaluate the effects of emergency protective action assumptions on the risk of prompt fatality and latent cancers fatality, and population relocation. The study finds that based on the new source terms the prompt and latent fatality risks at all generic sites meet the QHOs of the NRC`s Safety Goal Policy by margins ranging from one to more than three orders of magnitude. 4 refs., 17 figs., 24 tabs.

An evaluation of meteorologic data differences between the Pantex Plant and Amarillo, Texas

Energy Technology Data Exchange (ETDEWEB)

Snyder, S.F.

1993-06-01

Meteorologic data from the Pantex Plant and from the nearby National Weather Service (NWS) station at the Amarillo, Texas, International Airport were evaluated to determine if the NWS data adequately represented meteorologic conditions at the Pantex Plant. Annual site environmental dose calculations for the Pantex Plant have previously used the NWS data; information from this data comparison helped determine if future environmental dose calculations should use site-specific Pantex meteorologic data. The meteorologic data evaluated were wind speed, wind direction, and atmospheric stability class. Atmospheric stability class data were compared for years 1990 and 1991 and found to be very similar. Stability class designations were identical and one class different in 63% and 30%, respectively, of the paired hourly data. An unexpected finding was the preponderance of Class D stability, which occurred approximately 62% of the time in both data sets. The overall effect of meteorological differences between the two locations was evaluated by performing environmental dose assessments using the GENII dose assessment computer code. Acute and chronic releases of {sup 3}H and {sup 239}Pu were evaluated. Results using the NWS Amarillo meteorologic data were approximately one-half of those generated using Pantex meteorologic data. The two-fold difference in dose results is within the uncertainty expected from current dose assessment codes; therefore, the two meteorologic databases can be used interchangeably and prior dose calculation results using the NWS Amarillo data are acceptable.

The site of a nuclear power plant and environmental safety; Ydinvoimalaitoksen sijaintipaikka ja ympaeristoen turvallisuus

Energy Technology Data Exchange (ETDEWEB)

Rossi, J. [VTT Energy, Espoo (Finland)

2001-11-01

The purpose of this report is to give the reader a general view of the things associated with the site of a nuclear power plant. In this context the effect of a nuclear power plant and site on environmental safety is considered. Planning, construction and operating a nuclear power plant require several judgements and licenses based on different laws. The location of the planned nuclear facility project and environmental conditions contribute in great detail to the compliance arguments of permits. At first the environmental impacts of the siting project and its alternatives shall be investigated in the Environmental Impact Assessment procedure. Then the decision in principle according to the Nuclear Energy Act can be applied from the Council of State, the decision shall further be confirmed by Parliament. When the decision in principle is considered the overall good of society shall be assessed by means of considering i.a. site alternatives and safety. The safety related basic principle is that operation of a nuclear power plant may not cause danger to the environment, public or property. After the affirmative principle approval the construction license and later on the operation license can be applied from the Council of State, these licenses need to be supported i.a. by building and environmental licenses of separate authorities. Also some international contracts concern realisation of a nuclear power plant siting. The nuclear power plant site shall be suitable for the needs of the electricity production and the transmission system and it shall be technically appropriate for building and operation of a power plant. The site shall be safe enough on the other hand from the view of external events threatening the power plant - although one can be partly prepared for these things in the design of the plant - and on the other hand from the point of public safety. Requirements for the safety of the site are directed in the decision of the Council of State's general

Phytoremediation potential and ecological and phenological changes of native pioneer plants from weathered oil spill-impacted sites at tropical wetlands.

Science.gov (United States)

Palma-Cruz, Felipe de J; Pérez-Vargas, Josefina; Rivera Casado, Noemí Araceli; Gómez Guzmán, Octavio; Calva-Calva, Graciano

2016-08-01

Pioneer native plant species from weathered oil spill-affected sites were selected to study their potential for phytoremediation on the basis of their ecological and phenological changes during the phytoremediation process. Experiments were conducted in field and in greenhouse. In field, native plants from aged oil spill-impacted sites with up 400 g of weathered petroleum hydrocarbons per kilogram soil were selected. In the impacted sites, the principal dominant plant species with potential for hydrocarbons removal were Cyperus laxus, Cyperus esculentus, and Ludwigia peploides. In greenhouse, the phenology of the selected plant species was drastically affected by the hydrocarbons level above 325 g total petroleum hydrocarbons (TPH) per kilogram soil after 2 years of phytoremediation of soils from the aged oil spill-impacted sites. From the phytoremediation treatments, a mix-culture of C. laxus, C. esculentus, and L. peploides in soil containing 325 g TPH/kg soil, from which 20.3 % were polyaromatic hydrocarbons (PAH) and 34.2 % were asphaltenes (ASF), was able to remove up 93 % of the TPH, while in unvegetated soil the TPH removal was 12.6 %. Furthermore, evaluation of the biodiversity and life forms of plant species in the impacted sites showed that phytoremediation with C. esculentus, alone or in a mix-culture with C. laxus and L. peploides, reduces the TPH to such extent that the native plant community was progressively reestablished by replacing the cultivated species resulting in the ecological recovery of the affected soil. These results demonstrate that native Cyperus species from weathered oil spill-affected sites, specifically C. esculentus and C. laxus, alone or in a mix-culture, have particular potential for phytoremediation of soils from tropical wetlands contaminated with weathered oil hydrocarbons.

Hydraulic testing of Salado Formation evaporites at the Waste Isolation Pilot Plant site: Second interpretive report

Energy Technology Data Exchange (ETDEWEB)

Beauheim, R.L. [Sandia National Labs., Albuquerque, NM (United States); Roberts, R.M.; Dale, T.F.; Fort, M.D.; Stensrud, W.A. [INTERA, Inc., Austin, TX (United States)

1993-12-01

Pressure-pulse, constant-pressure flow, and pressure-buildup tests have been performed in bedded evaporites of the Salado Formation at the Waste Isolation Pilot Plant (WIPP) site to evaluate the hydraulic properties controlling brine flow through the Salado. Transmissivities have been interpreted from six sequences of tests conducted on five stratigraphic intervals within 15 m of the WIPP underground excavations.

Assessment procedure and probability determination methods of aircraft crash events in siting for nuclear power plants

International Nuclear Information System (INIS)

Zheng Qiyan; Zhang Lijun; Huang Weiqi; Yin Qingliao

2010-01-01

Assessment procedure of aircraft crash events in siting for nuclear power plants, and the methods of probability determination in two different stages of prelimi- nary screening and detailed evaluation are introduced in this paper. Except for general air traffic, airport operations and aircraft in the corridor, the probability of aircraft crash by military operation in the military airspaces is considered here. (authors)

Hydraulic testing of Salado Formation evaporites at the Waste Isolation Pilot Plant site: Second interpretive report

International Nuclear Information System (INIS)

Beauheim, R.L.; Roberts, R.M.; Dale, T.F.; Fort, M.D.; Stensrud, W.A.

1993-12-01

Pressure-pulse, constant-pressure flow, and pressure-buildup tests have been performed in bedded evaporites of the Salado Formation at the Waste Isolation Pilot Plant (WIPP) site to evaluate the hydraulic properties controlling brine flow through the Salado. Transmissivities have been interpreted from six sequences of tests conducted on five stratigraphic intervals within 15 m of the WIPP underground excavations

Ecological investigations at the Pantex Plant Site, 1992

International Nuclear Information System (INIS)

Cushing, C.E.; Mazaika, R.R.; Phillips, R.C.

1993-09-01

In 1992, Pantex requested that Pacific Northwest Laboratory (PNL) conduct a series of ecological surveys to provide baseline information for designing detailed ecological studies on the various ecosystems present at the Pantex plant site near Amarillo, Texas. To this end, PNL scientist and technicians visited the site at different times to conduct investigations and collect samples: July 6--13: birds, small mammals, general habitat assessment; August 10--14: wetland vegetation, birds, small mammals, Playa invertebrates; and September 7--11: birds, small mammals. This report presents the results of these three surveys

Environmentally acceptable endpoints for PAHs at a manufactured gas plant site

Energy Technology Data Exchange (ETDEWEB)

Stroo, H.F.; Jensen, R.; Loehr, R.C.; Nakles, D.V.; Fairbrother, A.; Liban, C.B. [ThermoRetec Corp., Carson, CA (USA)

2000-09-01

Samples from a former manufactured gas plant (MGP) site in Santa Barbara, CA were tested to evaluate the environmentally acceptable endpoints (EAE) process for setting risk-based cleanup criteria. The research was part of an ongoing effort to develop and demonstrate a protocol for assessing risk-based criteria for MGP sites that incorporates the availability of polycyclic aromatic hydrocarbons (PAHs). Six soil samples were subjected to a battery of physical and biological tests that focused on determining the 'availability' of the soil-bound contaminants to groundwater, ecological receptors, and human receptors. Results demonstrated that sorption to soil, matrix effects, aging, and treatment can significantly reduce chemical availability. Including these reduced availability results in risk assessment calculations yielded environmentally protective cleanup levels almost 3-10 times greater than levels derived using California default risk assessment assumptions. Using an EAE-based approach for MGP soils, especially those containing lampblack, could provide more realistic risk assessment. 23 refs., 6 tabs.

Analysis of extreme hydrometric values in the nuclear power plants siting

International Nuclear Information System (INIS)

Gomez, H.R.; Maggio, G.E.; Tripoli, C.R.

1983-01-01

The atucha nuclear power plants are located on the right shore of the Parana de las Palmas river in the entire transition between a fluvial regime and other of tides. Since the disponibility of cooling water is one of the factors to take into account when choosing the nuclear power plant site, it is essential to perform a probabilistic study of extreme hydrometric values. Deterministic and historical analysis should be done to complete the studies already mentioned, in order to establish the values of probable maximum floods. From the application of these methods, it is concluded that the site of the Atucha nuclear power plants constitutes a hydrometric singularity, so that, an optimization has been obtained from that point of view. (Author) [es

Influence of the crustal and subcrustal Vrancea seismic sources on Cernavoda nuclear power plant site

International Nuclear Information System (INIS)

Marmureanu, Gheorghe; Popescu, Emilia; Mircea Radulian

2002-01-01

The basis of the seismic hazard assessment in different geographical regions with dense-populated areas and strategic objectives (dams, nuclear power plants, etc.) is the study of seismicity of the seismogenic sources which affect these sites. The purpose of this paper is to provide a complete set of information relative to the Vrancea seismic source (in the crust and the intermediate depth domains) that is fundamental for the seismic hazard evaluation at Cernavoda nuclear power plant site. The analysis that we propose has to deal with the following items: (1) geometrical definition of the seismic sources; (2) setting the earthquake catalog associated to each seismic source; (3) estimation of the maximum possible magnitude; (4) estimation of the frequency - magnitude relationship; (5) computation of the distribution function for focal distance; (6) correlation between focal depth and magnitude; (7) attenuation law. We discuss also the implications of the model parameters on the seismic hazard level. (authors)

Waste Isolation Pilot Plant 2001 Site Environmental Report

Energy Technology Data Exchange (ETDEWEB)

Westinghouse TRU Solutions, Inc.

2002-09-20

The United States (U.S.) Department of Energy's (DOE) Carlsbad Field Office (CBFO) and Westinghouse TRU Solutions LLC (WTS) are dedicated to maintaining high quality management of Waste Isolation Pilot Plant (WIPP) environmental resources. DOE Order 5400.1, General Environmental Protection Program, and DOE Order 231.1, Environmental, Safety, and Health Reporting, require that the environment at and near DOE facilities be monitored to ensure the safety and health of the public and the environment. This Waste Isolation Pilot Plant 2001 Site Environmental Report summarizes environmental data from calendar year (CY) 2001 that characterize environmental management performance and demonstrate compliance with federal and state regulations. This report was prepared in accordance with DOE Order 5400.1, DOE Order 231.1, the Environmental Regulatory Guide for Radiological Effluent Monitoring and Environmental Surveillance (DOE/EH- 0173T), and the Waste Isolation Pilot Plant Environmental Protection Implementation Plan (DOE/WIPP 96-2199). The above Orders and guidance documents require that DOE facilities submit an annual site environmental report to DOE Headquarters, Office of the Assistant Secretary for Environment, Safety, and Health; and the New Mexico Environment Department (NMED). The purpose of this report is to provide a comprehensive description of operational environmental monitoring activities, to provide an abstract of environmental activities conducted to characterize site environmental management performance to confirm compliance with environmental standards and requirements, and to highlight significant programs and efforts of environmental merit at WIPP during CY 2001. WIPP received its first shipment of waste on March 26, 1999. In 2001, no evidence was found of any adverse effects from WIPP on the surrounding environment.

Waste Isolation Pilot Plant 2001 Site Environmental Report

International Nuclear Information System (INIS)

Westinghouse TRU Solutions, Inc.

2002-01-01

The United States (U.S.) Department of Energy's (DOE) Carlsbad Field Office (CBFO) and Westinghouse TRU Solutions LLC (WTS) are dedicated to maintaining high quality management of Waste Isolation Pilot Plant (WIPP) environmental resources. DOE Order 5400.1, General Environmental Protection Program, and DOE Order 231.1, Environmental, Safety, and Health Reporting, require that the environment at and near DOE facilities be monitored to ensure the safety and health of the public and the environment. This Waste Isolation Pilot Plant 2001 Site Environmental Report summarizes environmental data from calendar year (CY) 2001 that characterize environmental management performance and demonstrate compliance with federal and state regulations. This report was prepared in accordance with DOE Order 5400.1, DOE Order 231.1, the Environmental Regulatory Guide for Radiological Effluent Monitoring and Environmental Surveillance (DOE/EH- 0173T), and the Waste Isolation Pilot Plant Environmental Protection Implementation Plan (DOE/WIPP 96-2199). The above Orders and guidance documents require that DOE facilities submit an annual site environmental report to DOE Headquarters, Office of the Assistant Secretary for Environment, Safety, and Health; and the New Mexico Environment Department (NMED). The purpose of this report is to provide a comprehensive description of operational environmental monitoring activities, to provide an abstract of environmental activities conducted to characterize site environmental management performance to confirm compliance with environmental standards and requirements, and to highlight significant programs and efforts of environmental merit at WIPP during CY 2001. WIPP received its first shipment of waste on March 26, 1999. In 2001, no evidence was found of any adverse effects from WIPP on the surrounding environment

Waste Isolation Pilot Plant 1999 Site Environmental Report

Energy Technology Data Exchange (ETDEWEB)

Evans, Roy B.; Adams, Amy; Martin, Don; Morris, Randall C.; Reynolds, Timothy D.; Warren, Ronald W.

2000-09-30

The U.S. Department of Energy's (DOE)Carlsbad Area Office and the Westinghouse Waste Isolation Division (WID) are dedicated to maintaining high quality management of Waste Isolation Pilot Plant (WIPP) environmental resources. DOE Order 5400.1, General Environmental Protection Program, and DOE Order 231.1, Environmental, Safety, and Health Reporting, require that the environment at and near DOE facilities be monitored to ensure the safety and health of the public and the environment. This Waste Isolation Pilot Plant 1999 Site Environmental Report summarizes environmental data from calendar year 1999 that characterize environmental management performance and demonstrate compliance with federal and state regulations. This report was prepared in accordance with DOE Order 5400.1, DOE Order 231.1, the Environmental Regulatory Guide for Radiological Effluent Monitoring and Environmental Surveillance (DOE/EH- 0173T), and the Waste Isolation Pilot Plant Environmental Protection Implementation Plan (DOE/WIPP 96-2199). The above orders and guidance documents require that DOE facilities submit an Annual Site Environmental Report to DOE Headquarters, Office of the Assistant Secretary for Environment, Safety, and Health. The purpose of this report is to provide a comprehensive description of operational environmental monitoring activities, to provide an abstract of environmental activities conducted to characterize site environmental management performance to confirm compliance with environmental standards and requirements, and to highlight significant programs and efforts of environmental merit at WIPP during calendar year 1999. WIPP received its first shipment of waste on March 26, 1999. In 1999, no evidence was found of any adverse effects from WIPP on the surrounding environment. Radionuclide concentrations in the environment surrounding WIPP were not statistically higher in 1999 than in 1998.

The subject deserving wide attention for nuclear power plant siting and environmental impact assessment

International Nuclear Information System (INIS)

Li Yong; Li Wenhui; Zhang Lingyan

2009-01-01

Based on siting work of nuclear power plant, the characteristics of nuclear power plant site selection and environmental impact assessment are analysed in accordance with laws and regulations of nuclear safety and environmental protection. Some subjects deserving attentions are put forward. (authors)

Site infrastructure as required during the construction and erection of nuclear power plants

International Nuclear Information System (INIS)

Haas, K.F.; Wagner, H.

1978-01-01

In general, in an exchange of experience on constructing nuclear power plants priority is given to design and lay-out, financing, quality assurance etc., but in this paper an attempt has been made to describe range and type of site infrastructure required during construction and erection. Site infrastructure will make considerable demands on the planning, supply of material and maintenance that may result from the frequently very isolated location of power plant sites. Examples for specific values and experiences are given for a nuclear power plant with two units on the 1300-MW type at present under construction of the Persian Gulf in Iran. Data concerning the site infrastructure, including examples, are given and explained on the basis of graphs. The site is split up into a technical and a social infrastructure. The main concern of the technical site infrastructure is the timely provision and continuous availability of electric energy, water, communication grids, workshops, warehouses, offices, transport and handling facilities, as well as the provision of heavy load roads, harbour facilities, etc. The social site infrastructure in general comprises accommodation, food supplies and the care and welfare of all site personnel, which includes a hospital, school, self-service shop, and sport and recreation facilities. (author)

Waste Isolation Pilot Plant site environmental report for calendar year 1994

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-06-01

US Department of Energy (DOE) Order 5400.1 General Environmental Protection Program, requires each DOE facility that conducts significant environmental protection programs to prepare an Annual Site Environmental Report (ASER). The purpose of the ASER is to summarize environmental data in order to characterize site environmental management performance, to confirm compliance with environmental standards and requirements, and to highlight significant programs and efforts. This ASER not only documents the required data, it also documents new and continued monitoring and compliance activities during the 1994 calendar year. Data contained in this report are derived from those monitoring programs directed by the Waste Isolation Pilot Plant (WIPP) Environmental Monitoring Plan (EMP) (DOE/WIPP 94-024). The EMP defines a comprehensive set of parameters that must be monitored to detect potential impacts to the environment and to establish baseline measurements for future environmental evaluations. Surface water, groundwater, air, soil, and biotics are monitored for radiological and nonradiological activity levels. The baseline radiological surveillance program covers the broader geographic area that encompasses nearby ranches, villages, and cities. Nonradiological studies focus on the area immediately surrounding the WIPP site.

Waste Isolation Pilot Plant site environmental report for calendar year 1994

International Nuclear Information System (INIS)

1995-06-01

US Department of Energy (DOE) Order 5400.1 General Environmental Protection Program, requires each DOE facility that conducts significant environmental protection programs to prepare an Annual Site Environmental Report (ASER). The purpose of the ASER is to summarize environmental data in order to characterize site environmental management performance, to confirm compliance with environmental standards and requirements, and to highlight significant programs and efforts. This ASER not only documents the required data, it also documents new and continued monitoring and compliance activities during the 1994 calendar year. Data contained in this report are derived from those monitoring programs directed by the Waste Isolation Pilot Plant (WIPP) Environmental Monitoring Plan (EMP) (DOE/WIPP 94-024). The EMP defines a comprehensive set of parameters that must be monitored to detect potential impacts to the environment and to establish baseline measurements for future environmental evaluations. Surface water, groundwater, air, soil, and biotics are monitored for radiological and nonradiological activity levels. The baseline radiological surveillance program covers the broader geographic area that encompasses nearby ranches, villages, and cities. Nonradiological studies focus on the area immediately surrounding the WIPP site

How do young people evaluate nuclear energy at nuclear power plant sites? An empirical study; Wie bewerten junge Menschen an Standorten von Kernkraftwerken die Kernenergie? Eine empirische Studie

Energy Technology Data Exchange (ETDEWEB)

Kretz, Simon [Karlsruher Institut fuer Technologie (KIT), Karlsruhe (Germany). Inst. fuer Geographie und Geooekologie; Kramer, Caroline [Karlsruher Institut fuer Technologie (KIT), Karlsruhe (Germany). Professur fuer Humangeographie

2014-12-15

How does the younger generation evaluate nuclear power at sites with nuclear power plants? This has been examined at four sites with different decommissioning stages, as the presence of a nuclear power plant in young people's daily life represents a potential employer as well as a potential risk factor. The attitude of this generation will expectedly and sustainably influence the development of communities. The decommissioning of a nuclear power plant is currently, optimistically estimated by different energy supplying companies with a time period of 15 to 20 year. Thus the resident population will deal with this topic until the year 2040. Furthermore the decision on a repository exploration has been sighted for the year 2013. As a final repository will not be ready for operation at that time, communities will have to deal with the storage of radioactive waste in local interim-storage facilities. The next generation has the opportunity to shape their future as well as the future of their community. Nevertheless the preconditions are to stay at the side as well as the political and social engagement of these young people. n order to study this aspect and the opportunities of action of young people, data was gathered by carrying out a standardised survey, interviewing 762 pupils in February 2014.

Site fidelity by bees drives pollination facilitation in sequentially blooming plant species.

Science.gov (United States)

Ogilvie, Jane E; Thomson, James D

2016-06-01

Plant species can influence the pollination and reproductive success of coflowering neighbors that share pollinators. Because some individual pollinators habitually forage in particular areas, it is also possible that plant species could influence the pollination of neighbors that bloom later. When flowers of a preferred forage plant decline in an area, site-fidelity may cause individual flower feeders to stay in an area and switch plant species rather than search for preferred plants in a new location. A newly blooming plant species may quickly inherit a set of visitors from a prior plant species, and therefore experience higher pollination success than it would in an area where the first species never bloomed. To test this, we manipulated the placement and timing of two plant species, Delphinium barbeyi and later-blooming Gentiana parryi. We recorded the responses of individually marked bumble bee pollinators. About 63% of marked individuals returned repeatedly to the same areas to forage on Delphinium. When Delphinium was experimentally taken out of bloom, most of those site-faithful individuals (78%) stayed and switched to Gentiana. Consequently, Gentiana flowers received more visits in areas where Delphinium had previously flowered, compared to areas where Delphinium was still flowering or never occurred. Gentiana stigmas received more pollen in areas where Delphinium disappeared than where it never bloomed, indicating that Delphinium increases the pollination of Gentiana when they are separated in time. Overall, we show that individual bumble bees are often site-faithful, causing one plant species to increase the pollination of another even when separated in time, which is a novel mechanism of pollination facilitation.

Design basis flood for nuclear power plants on coastal sites

International Nuclear Information System (INIS)

1983-01-01

This Guide discusses the phenomena causing coastal floods (storm surge, seiche, tsunami and wind-wave) and gives a general description of the methods used and the critical factors involved in the evaluation of such floods and of their associated effects. In addition, some treatment is presented of the possible combinations of two or more of these phenomena to produce a DBF. Methods are also provided for evaluating the reference water levels, taking into account the effect of tides, sea level anomalies and changes in lake level and river flow. Sites vulnerable to coastal flooding are located on open coastal regions, semi-enclosed bodies of water and enclosed bodies of water. Open coastal regions are those portions of land directly exposed to and having a shore on a major body of water. Semi-enclosed bodies of water are lagoons, river estuaries, gulfs, fjords and rias. Enclosed bodies of water are lakes and reservoirs. The phenomena of the lowering of the water level at coastal sites caused by offshore winds, low tides, wave effects or of drawdown caused by tsunamis are discussed. The static and dynamic effects of floods resulting from the various combinations (independent and interdependent) of surface waves of varying frequency are also discussed. Consideration is also given to shoreline instabilities and to the effects of erosion. Estimated flood levels and related effects on the nuclear power plant, which will vary according to the method of analysis and the type of flooding considered, shall be compared with available historical data where this is relevant, to check the conservativeness of the evaluated results

Plant operator performance evaluation system

International Nuclear Information System (INIS)

Ujita, Hiroshi; Fukuda, Mitsuko; Kubota, Ryuji.

1989-01-01

A plant operator performance evaluation system to analyze plant operation records during accident training and to identify and classify operator errors has been developed for the purpose of supporting realization of a training and education system for plant operators. A knowledge engineering technique was applied to evaluation of operator behavior by both even-based and symptom-based procedures, in various situations including event transition due to multiple failures or operational errors. The system classifies the identified errors as to their single and double types based on Swain's error classification and the error levels reflecting Rasmussen's cognitive level, and it also evaluates the effect of errors on plant state and then classifies error influence, using 'knowledge for phenomena and operations', as represented by frames. It has additional functions for analysis of error statistics and knowledge acquisition support of 'knowledge for operations'. The system was applied to a training analysis for a scram event in a BWR plant, and its error analysis function was confirmed to be effective by operational experts. (author)

Perryman Nuclear Power Plant. Site suitability--site safety report, volume I: chapters-sections 1.1, 1.2, 1.4, 1.6; 2.1, 2.2

International Nuclear Information System (INIS)

1977-01-01

A site suitability report is submitted in support of the Baltimore Gas and Electric Company application for a limited early site review of a potential nuclear power plant. The Perryman Nuclear Power Plant site is located in northeastern Maryland on an arm of the Chesapeake Bay estuary approximately 17 miles east--northeast of Baltimore. The proposed plant is a two-unit light water reactor with a 3800 MW(t) power level for each unit. General descriptions of the site geography, demography, nearby facilities, and meteorology are presented

Illumina amplicon sequencing of 16S rRNA tag reveals bacterial community development in the rhizosphere of apple nurseries at a replant disease site and a new planting site.

Directory of Open Access Journals (Sweden)

Jian Sun

Full Text Available We used a next-generation, Illumina-based sequencing approach to characterize the bacterial community development of apple rhizosphere soil in a replant site (RePlant and a new planting site (NewPlant in Beijing. Dwarfing apple nurseries of 'Fuji'/SH6/Pingyitiancha trees were planted in the spring of 2013. Before planting, soil from the apple rhizosphere of the replant site (ReSoil and from the new planting site (NewSoil was sampled for analysis on the Illumina MiSeq platform. In late September, the rhizosphere soil from both sites was resampled (RePlant and NewPlant. More than 16,000 valid reads were obtained for each replicate, and the community was composed of five dominant groups (Proteobacteria, Acidobacteria, Bacteroidetes, Gemmatimonadetes and Actinobacteria. The bacterial diversity decreased after apple planting. Principal component analyses revealed that the rhizosphere samples were significantly different among treatments. Apple nursery planting showed a large impact on the soil bacterial community, and the community development was significantly different between the replanted and newly planted soils. Verrucomicrobia were less abundant in RePlant soil, while Pseudomonas and Lysobacter were increased in RePlant compared with ReSoil and NewPlant. Both RePlant and ReSoil showed relatively higher invertase and cellulase activities than NewPlant and NewSoil, but only NewPlant soil showed higher urease activity, and this soil also had the higher plant growth. Our experimental results suggest that planting apple nurseries has a significant impact on soil bacterial community development at both replant and new planting sites, and planting on new site resulted in significantly higher soil urease activity and a different bacterial community composition.

Subcellular site and nature of intracellular cadmium in plants

International Nuclear Information System (INIS)

Wagner, G.J.

1979-01-01

The mechanisms underlying heavy metal accumulation, toxicity, and tolerance in higher plants are poorly understood. Since subcellular processes are undoubtedly involved in all these phenomena, it is of interest to study the extent, subcellular site and nature of intracellularly accumulated cadmium in higher plants. Whole plants supplied 109 CdCl 2 or 112 CdSO 4 accumulated Cd into roots and aerial tissues. Preparation of protoplasts from aerial tissues followed by subcellular fractionation of the protoplasts to obtain intact vacuoles, chloroplasts and cytosol revealed the presence of Cd in the cytosol but not in vacuoles or chloroplasts. No evidence was obtained for the production of volatile Cd complexes in tobacco

International Thermonuclear Experimental Reactor (ITER) plant layout and site services

International Nuclear Information System (INIS)

Chuyanov, V.

2001-01-01

The ITER site has not been determined at this time. Nevertheless, to develop a construction plan and a cost estimate, it is necessary to have a detailed layout of the buildings, structures, and outdoor equipment integrated with the balance of plant service systems prototypical of large fusion power plants. These services include electric power for magnet feeds and plasma heating systems, cryogenic and conventional cooling systems, compressed air, gas supplies, de-mineralized water, steam, and drainage. Nuclear grade facilities are provided to handle tritium fuel and activated waste, as well as to prevent radioactive exposure of either the workers or the public. To avoid interference between services of different types and for efficient arrangement of buildings, structures, and equipment within the site area, a plan was developed which segregated different classes of services to four quadrants surrounding the tokamak building, placed at the approximate geographic center of the site. Location of the twenty-seven buildings on the generic site was selected to meet all design requirements at minimum total project cost. A similar approach has been used to determine the location of services above, at, and below grade. The generic site plan can be adapted to the site selected for ITER without significant changes to the buildings or equipment. Some rearrangements may be required by site topography resulting primarily in changes to the length of services that link the buildings and equipment. (author)

International Thermonuclear Experimental Reactor (ITER) plant layout and site services

International Nuclear Information System (INIS)

Chuyanov, V.

1999-01-01

The ITER site has not been determined at this time. Nevertheless, to develop a construction plan and a cost estimate, it is necessary to have a detailed layout of the buildings, structures, and outdoor equipment integrated with the balance of plant service systems prototypical of large fusion power plants. These services include electric power for magnet feeds and plasma heating systems, cryogenic and conventional cooling systems, compressed air, gas supplies, de-mineralized water, steam, and drainage. Nuclear grade facilities are provided to handle tritium fuel and activated waste, as well as to prevent radioactive exposure of either the workers or the public. To avoid interference between services of different types and for efficient arrangement of buildings, structures, and equipment within the site area, a plan was developed which segregated different classes of services to four quadrants surrounding the tokamak building, placed at the approximate geographic center of the site. Location of the twenty-seven buildings on the generic site was selected to meet all design requirements at minimum total project cost. A similar approach has been used to determine the location of services above, at, and below grade. The generic site plan can be adapted to the site selected for ITER without significant changes to the buildings or equipment. Some rearrangements may be required by site topography resulting primarily in changes to the length of services that link the buildings and equipment. (author)

Review of Investigations on Site Selection for Nuclear Power Plants in Croatia

Energy Technology Data Exchange (ETDEWEB)

Malbasa, N [Ekonerg, Zagreb (Croatia)

2008-07-01

A review of site investigation for nuclear facilities in the Republic of Croatia that had been performed from 1964, when investigation started for the first nuclear power plant, to 1994 when the activities were stopped, is presented therein. Brief results of the main investigation were presented including the Tanja site on the Danube upstream of Vukovar. It is the best of all the investigated locations for nuclear power plant in Croatia. The review of results for site selection of low and intermediate level of radioactive waste disposal is also given. The position of nuclear power plants in the strategic documents of the Republic of Croatia was analysed. It is concluded that the status of nuclear facilities in the main strategic documents must be improved because the energy future in Croatia - as almost in all European countries - could hardly be successful without any further development of nuclear energy.(author)

Review of Investigations on Site Selection for Nuclear Power Plants in Croatia

International Nuclear Information System (INIS)

Malbasa, N.

2008-01-01

A review of site investigation for nuclear facilities in the Republic of Croatia that had been performed from 1964, when investigation started for the first nuclear power plant, to 1994 when the activities were stopped, is presented therein. Brief results of the main investigation were presented including the Tanja site on the Danube upstream of Vukovar. It is the best of all the investigated locations for nuclear power plant in Croatia. The review of results for site selection of low and intermediate level of radioactive waste disposal is also given. The position of nuclear power plants in the strategic documents of the Republic of Croatia was analysed. It is concluded that the status of nuclear facilities in the main strategic documents must be improved because the energy future in Croatia - as almost in all European countries - could hardly be successful without any further development of nuclear energy.(author)

Development of the on-site power supply in German nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Simon, M. [Gesellschaft fuer Reaktorsicherheit - GRS mbH, Schwertnergasse 1, D-5000 Koeln 1, Cologne (Germany)

1986-02-15

The design of the on-site power supply is different in German Nuclear Power Plants, depending on age and size of the plant. The cause for this is the evolution of the safety requirements. The general development of the design of safety Systems, which resulted in a strict separation of redundant trains is also reflected in the design of the emergency power system and even the complete on-site power supply System. This will be demonstrated by different examples. The advantages of this design with respect to the availability of on-site power will be explained and verified by means of operating experience. (author)

An assessment and evaluation for recycle/reuse of contaminated process and metallurgical equipment at the DOE Rocky Flats Plant Site -- Building 865. Final report

Energy Technology Data Exchange (ETDEWEB)

1993-08-01

An economic analysis of the potential advantages of alternatives for recycling and reusing equipment now stored in Building 865 at the Rocky Flats Plant (RFP) in Colorado has been conducted. The inventory considered in this analysis consists primarily of metallurgical and process equipment used before January 1992, during development and production of nuclear weapons components at the site. The economic analysis consists of a thorough building inventory and cost comparisons for four equipment dispositions alternatives. The first is a baseline option of disposal at a Low Level Waste (LLW) landfill. The three alternatives investigated are metal recycling, reuse with the government sector, and release for unrestricted use. This report provides item-by-item estimates of value, disposal cost, and decontamination cost. The economic evaluation methods documented here, the simple cost comparisons presented, and the data provided as a supplement, should provide a foundation for D&D decisions for Building 865, as well as for similar D&D tasks at RFP and at other sites.

Waste Isolation Pilot Plant CY 2000 Site Environmental Report

International Nuclear Information System (INIS)

Westinghouse TRU Solutions, LLC; Environmental Science and Research Foundation, Inc.

2001-01-01

The U.S. Department of Energy's (DOE) Carlsbad Field Office and Westinghouse TRU Solutions, LLC (WTS) are dedicated to maintaining high quality management of Waste Isolation Pilot Plant (WIPP) environmental resources. DOE Order 5400.1, General Environmental Protection Program, and DOE Order 231.1, Environmental, Safety, and Health Reporting, require that the environment at and near DOE facilities be monitored to ensure the safety and health of the public and the environment. This Waste Isolation Pilot Plant 2000 Site Environmental Report summarizes environmental data from calendar year (CY) 2000 that characterize environmental management performance and demonstrate compliance with federal and state regulations. This report was prepared in accordance with DOE Order 5400.1, DOE Order 231.1, the Environmental Regulatory Guide for Radiological Effluent Monitoring and Environmental Surveillance (DOE/EH-0173T), and the Waste Isolation Pilot Plant Environmental Protect ion Implementation Plan (DOE/WIPP 96-2199). The above orders and guidance documents require that DOE facilities submit an Annual Site Environmental Report to DOE Headquarters, Office of the Assistant Secretary for Environment, Safety, and Health. The purpose of this report is to provide a comprehensive description of operational environmental monitoring activities, to provide an abstract of environmental activities conducted to characterize site environmental management performance to confirm compliance with environmental standards and requirements, and to highlight significant programs and efforts of environmental merit at WIPP during CY 2000. The format of this report follows guidance offered in a June 1, 2001 memo from DOE's Office of Policy and Guidance with the subject ''Guidance for the preparation of Department of Energy (DOE) Annual Site Environmental Reports (ASERs) for Calendar Year 2000.'' WIPP received its first shipment of waste on March 26, 1999. In 2000, no evidence was found of any adverse

Waste Isolation Pilot Plant CY 2000 Site Environmental Report

Energy Technology Data Exchange (ETDEWEB)

Westinghouse TRU Solutions, LLC; Environmental Science and Research Foundation, Inc.

2001-12-31

The U.S. Department of Energy's (DOE) Carlsbad Field Office and Westinghouse TRU Solutions, LLC (WTS) are dedicated to maintaining high quality management of Waste Isolation Pilot Plant (WIPP) environmental resources. DOE Order 5400.1, General Environmental Protection Program, and DOE Order 231.1, Environmental, Safety, and Health Reporting, require that the environment at and near DOE facilities be monitored to ensure the safety and health of the public and the environment. This Waste Isolation Pilot Plant 2000 Site Environmental Report summarizes environmental data from calendar year (CY) 2000 that characterize environmental management performance and demonstrate compliance with federal and state regulations. This report was prepared in accordance with DOE Order 5400.1, DOE Order 231.1, the Environmental Regulatory Guide for Radiological Effluent Monitoring and Environmental Surveillance (DOE/EH-0173T), and the Waste Isolation Pilot Plant Environmental Protect ion Implementation Plan (DOE/WIPP 96-2199). The above orders and guidance documents require that DOE facilities submit an Annual Site Environmental Report to DOE Headquarters, Office of the Assistant Secretary for Environment, Safety, and Health. The purpose of this report is to provide a comprehensive description of operational environmental monitoring activities, to provide an abstract of environmental activities conducted to characterize site environmental management performance to confirm compliance with environmental standards and requirements, and to highlight significant programs and efforts of environmental merit at WIPP during CY 2000. The format of this report follows guidance offered in a June 1, 2001 memo from DOE's Office of Policy and Guidance with the subject ''Guidance for the preparation of Department of Energy (DOE) Annual Site Environmental Reports (ASERs) for Calendar Year 2000.'' WIPP received its first shipment of waste on March 26, 1999. In 2000, no

Site selection of a dual purpose nuclear power plant in Saudi Arabia

International Nuclear Information System (INIS)

Hussein, F.M.; Obeid, M.A.; El-Malahy, K.S.

1987-01-01

Selecting a nuclear power plant site for power production and water desalination is a very complex problem, especially in countries with moderate technology. Many interrelated factors affect the process, and professional judgments by various experts are involved. Four sites, all located on the West Coast of Saudi Arabia along the Red Sea, were chosen as potential sites for building such a plant. (All sites were in either the northern or southern section of the coast; the central part was excluded for pilgrims' safety.) The East Coast was completely eliminated in the initial screening process due to its strategic location, the existence of oil fields and refineries, and its proximity to other Arabian (Persian) Gulf countries (to minimize radioactive releases to these countries in case of an accident). A computer code based on Saaty's eigenvalue technique and developed in a previous study was used in this analysis. Twenty-one main criteria were considered, and the sites were ranked to determine which was most desirable. Site 4 was found to be most suitable, followed by site 3

Pinellas Plant annual site environmental report for calendar year 1993

International Nuclear Information System (INIS)

1994-01-01

Martin Marietta Specialty Components, Inc., and the US Department of Energy are committed to successfully administering a high quality Environmental Management Program at the Pinellas Plant in Pinellas County, Florida. Part of this commitment includes accurately documenting and communicating to the Pinellas Plant stakeholder the results of their environmental compliance and monitoring activities. The Annual Site Environmental Report presents a comprehensive summary of the results of the environmental monitoring, waste management, and environmental restoration programs at the Pinellas Plant for 1993. This report also includes the plant's performance in the areas of compliance with applicable regulatory requirements and standards and identifies major environmental management program initiatives and accomplishments for 1993

Earthquakes and associated topics in relation to nuclear power plant siting

International Nuclear Information System (INIS)

1991-01-01

This Safety Guide was prepared as part of the Agency's programme for establishing Codes and Safety Guides relating to nuclear power plants. The main purpose of the text is to provide guidance on the determination of the design basis ground motions for a nuclear power plant at a chosen site and on the determination of the potential for surface faulting at that site. Additionally, the Guide discusses other permanent displacement phenomena (liquefaction, slope instability, subsidence and collapse) and introduces the topic of seismically induced flooding. Volcanic activity is not dealt with except in connection with tsunamis. 55 refs

Site-specific proteolytic degradation of IgG monoclonal antibodies expressed in tobacco plants.

Science.gov (United States)

Hehle, Verena K; Lombardi, Raffaele; van Dolleweerd, Craig J; Paul, Mathew J; Di Micco, Patrizio; Morea, Veronica; Benvenuto, Eugenio; Donini, Marcello; Ma, Julian K-C

2015-02-01

Plants are promising hosts for the production of monoclonal antibodies (mAbs). However, proteolytic degradation of antibodies produced both in stable transgenic plants and using transient expression systems is still a major issue for efficient high-yield recombinant protein accumulation. In this work, we have performed a detailed study of the degradation profiles of two human IgG1 mAbs produced in plants: an anti-HIV mAb 2G12 and a tumour-targeting mAb H10. Even though they use different light chains (κ and λ, respectively), the fragmentation pattern of both antibodies was similar. The majority of Ig fragments result from proteolytic degradation, but there are only a limited number of plant proteolytic cleavage events in the immunoglobulin light and heavy chains. All of the cleavage sites identified were in the proximity of interdomain regions and occurred at each interdomain site, with the exception of the VL /CL interface in mAb H10 λ light chain. Cleavage site sequences were analysed, and residue patterns characteristic of proteolytic enzymes substrates were identified. The results of this work help to define common degradation events in plant-produced mAbs and raise the possibility of predicting antibody degradation patterns 'a priori' and designing novel stabilization strategies by site-specific mutagenesis. © 2014 Society for Experimental Biology, Association of Applied Biologists and John Wiley & Sons Ltd.

Hydrologic investigations to evaluate a potential site for a nuclear-waste repository, Yucca Mountain, Nevada Test Site

International Nuclear Information System (INIS)

Wilson, W.E.

1985-01-01

Yucca Mountain, Nevada Test Site, is being evaluated by the U.S. Department of Energy for its suitability as a site for a mined geologic respository for high-level nuclear wastes. The repository facility would be constructed in densely welded tuffs in the unsaturated zone. In support of the evaluation, the U.S. Geological Survey is conducting hydrologic investigations of both the saturated and unsaturated zones, as well as paleohydrologic studies. Investigation in saturated-zone hydrology will help define one component of ground-water flow paths and travel times to the accessible environment. A two-dimensional, steady-state, finite-element model was developed to describe the regional hydrogeologic framework. The unsaturated zone is 450 to 700 meters thick at Yucca Mountain; precipitation averages about 150 millimeters per year. A conceptual hydrologic model of the unsaturated zone incorporates the following features: minimal net infiltration, variable distribution of flux, lateral flow, potential for perched-water zones, fracture and matrix flow, and flow along faults. The conceptual model is being tested primarily by specialized test drilling; plans also are being developed for in-situ testing in a proposed exploratory shaft. Quaternary climatic and hydrologic conditions are being evaluated to develop estimates of the hydrologic effects of potential climatic changes during the next 10,000 years. Evaluation approaches include analysis of plant macrofossils in packrat middens, evaluation of lake and playa sediments, infiltration tests, and modeling effects of potential increased recharge on the potentiometric surface

Early Site Permit Demonstration Program: Regulatory criteria evaluation report

Energy Technology Data Exchange (ETDEWEB)

1993-03-01

The primary objective of the ESPDP is to demonstrate successfully the use of 10CFR52 to obtain ESPs for one or more US sites for one (or more) ALWR nuclear power plants. It is anticipated that preparation of the ESP application and interaction with NRC during the application review process will result not only in an ESP for the applicant(s) but also in the development of criteria and definition of processes, setting the precedent that facilitates ESPs for subsequent ESP applications. Because siting regulatory processes and acceptance criteria are contained in over 100 separate documents, comprehensive licensing and technical reviews were performed to establish whether the requirements and documentation are self-consistent, whether the acceptance criteria are sufficiently well-defined and clear, and whether the licensing process leading to the issuance of an ESP is unambiguously specified. The results of the technical and licensing evaluations are presented in this report. The purpose, background, and organization of the ESPDP is delineated in Section 1. Section 11 contains flowcharts defining siting application requirements, environmental report requirements, and emergency planning/preparedness requirements for ALWRS. The licensing and technical review results are presented in Section III.

Early Site Permit Demonstration Program: Regulatory criteria evaluation report

International Nuclear Information System (INIS)

1993-03-01

The primary objective of the ESPDP is to demonstrate successfully the use of 10CFR52 to obtain ESPs for one or more US sites for one (or more) ALWR nuclear power plants. It is anticipated that preparation of the ESP application and interaction with NRC during the application review process will result not only in an ESP for the applicant(s) but also in the development of criteria and definition of processes, setting the precedent that facilitates ESPs for subsequent ESP applications. Because siting regulatory processes and acceptance criteria are contained in over 100 separate documents, comprehensive licensing and technical reviews were performed to establish whether the requirements and documentation are self-consistent, whether the acceptance criteria are sufficiently well-defined and clear, and whether the licensing process leading to the issuance of an ESP is unambiguously specified. The results of the technical and licensing evaluations are presented in this report. The purpose, background, and organization of the ESPDP is delineated in Section 1. Section 11 contains flowcharts defining siting application requirements, environmental report requirements, and emergency planning/preparedness requirements for ALWRS. The licensing and technical review results are presented in Section III

Earthworms drive succession of both plant and Collembola communities in post-mining sites

Science.gov (United States)

Mudrák, Ondřej; Uteseny, Karoline; Frouz, Jan

2016-04-01

Previous field observations indicated that earthworms promote late-successional plant species and reduce collembolan numbers at post-mining sites in the Sokolov coal mining district (Czech Republic). Here, we established a laboratory pot experiment to test the effect of earthworms (Aporrectodea caliginosa Savigny and Lumbricus rubellus Hoffm.) and litter of low, medium, and high quality (the grass Calamagrostis epigejos, the willow Salix caprea, and the alder Alnus glutinosa, respectively) on late successional plants (grasses Arrhenatherum elatius and Agrostis capillaris, legumes Lotus corniculatus and Trifolium medium, and non-leguminous dicots Centaurea jacea and Plantago lanceolata) in spoil substrate originating from Sokolov post-mining sites and naturally inhabited by abundant numbers of Collembola. The earthworms increased plant biomass, especially that of the large-seeded A. elatius, but reduced the number of plant individuals, mainly that of the small-seeded A. capillaris and both legumes. Litter quality affected plant biomass, which was highest with S. caprea litter, but did not change the number of plant individuals. Litter quality did not modify the effect of earthworms on plants; the effect of litter quality and earthworms was only additive. Species composition of Collembola community was altered by litter quality, but earthworms reduced the number of individuals, increased the number of species, and increased species evenness consistently across the litter qualities. Because the results of this experiment were consistent with the field observations, we conclude that earthworms help drive succession of both plant and Collembola communities on post-mining sites.

Report of early site suitability evaluation of the potential repository site at Yucca Mountain, Nevada; Yucca Mountain Site Characterization Project

Energy Technology Data Exchange (ETDEWEB)

Younker, J.L.; Andrews, W.B.; Fasano, G.A.; Herrington, C.C.; Mattson, S.R.; Murray, R.C. [Science Applications International Corp., Las Vegas, NV (United States); Ballou, L.B.; Revelli, M.A. [Lawrence Livermore National Lab., CA (United States); Ducharme, A.R.; Shephard, L.E. [Sandia National Labs., Albuquerque, NM (United States); Dudley, W.W.; Hoxie, D.T. [Geological Survey, Denver, CO (United States); Herbst, R.J.; Patera, E.A. [Los Alamos National Lab., NM (United States); Judd, B.R. [Decision Analysis Co., Portola Valley, CA (United States); Docka, J.A.; Rickertsen, L.D. [Weston Technical Associates, Washington, DC (United States)

1992-01-01

This study evaluated the technical suitability of Yucca Mountain, Nevada, as a potential site for a mined geologic repository for the permanent disposal of radioactive waste. The evaluation was conducted primarily to determine early in the site characterization program if there are any features or conditions at the site that indicate it is unsuitable for repository development. A secondary purpose was to determine the status of knowledge in the major technical areas that affect the suitability of the site. This early site suitability evaluation (ESSE) was conducted by a team of technical personnel at the request of the Associate Director of the US Department of Energy (DOE) Office of Geologic Disposal, a unit within the DOE`s Office of Civilian Radioactive Waste Management. The Yucca Mountain site has been the subject of such evaluations for over a decade. In 1983, the site was evaluated as part of a screening process to identify potentially acceptable sites. The site was evaluated in greater detail and found suitable for site characterization as part of the Environmental Assessment (EA) (DOE, 1986) required by the Nuclear Waste Policy Act of 1982 (NWPA). Additional site data were compiled during the preparation of the Site Characterization Plan (SCP) (DOE, 1988a). This early site suitability evaluation has considered information that was used in preparing both-documents, along with recent information obtained since the EA and SCP were published. This body of information is referred to in this report as ``current information`` or ``available evidence.``

Report of early site suitability evaluation of the potential repository site at Yucca Mountain, Nevada

International Nuclear Information System (INIS)

Younker, J.L.; Andrews, W.B.; Fasano, G.A.; Herrington, C.C.; Mattson, S.R.; Murray, R.C.; Ballou, L.B.; Revelli, M.A.; Ducharme, A.R.; Shephard, L.E.; Dudley, W.W.; Hoxie, D.T.; Herbst, R.J.; Patera, E.A.; Judd, B.R.; Docka, J.A.; Rickertsen, L.D.

1992-01-01

This study evaluated the technical suitability of Yucca Mountain, Nevada, as a potential site for a mined geologic repository for the permanent disposal of radioactive waste. The evaluation was conducted primarily to determine early in the site characterization program if there are any features or conditions at the site that indicate it is unsuitable for repository development. A secondary purpose was to determine the status of knowledge in the major technical areas that affect the suitability of the site. This early site suitability evaluation (ESSE) was conducted by a team of technical personnel at the request of the Associate Director of the US Department of Energy (DOE) Office of Geologic Disposal, a unit within the DOE's Office of Civilian Radioactive Waste Management. The Yucca Mountain site has been the subject of such evaluations for over a decade. In 1983, the site was evaluated as part of a screening process to identify potentially acceptable sites. The site was evaluated in greater detail and found suitable for site characterization as part of the Environmental Assessment (EA) (DOE, 1986) required by the Nuclear Waste Policy Act of 1982 (NWPA). Additional site data were compiled during the preparation of the Site Characterization Plan (SCP) (DOE, 1988a). This early site suitability evaluation has considered information that was used in preparing both-documents, along with recent information obtained since the EA and SCP were published. This body of information is referred to in this report as ''current information'' or ''available evidence.''

Evaluation of the impact of 1983 east sea tsunami at the site of Ulchin nuclear power plant

International Nuclear Information System (INIS)

Lee, H. K.; Lee, D. S.; Choi, S. H.

2001-01-01

In the past, we carried out the safety assessment study at the site of Ulchin NPP against tsunamis on the basis of maximum earthquake magnitude 7 3/4 and available tsunamigenic earthquake fault parameters. But, recently, based on the seismic gap theory some geologists and seismologists warned that the earthquakes with larger magnitude than was expected might occur in the East Sea region. And, the need of re-evaluation of safety is suggested. In this study, to investigate the applicability of a finite difference model, we simulated the 1983 East Sea Tsunami at the Imwon Harbor where the maximum run-up height of tsunami was observed. The general agreement was obtained in the viewpoint of maxium wave run-up height. Finally, we evaluated the rise and drop of sea water level at the site of Ulchin NPP and concluded that the site of Ulchin NPP is safe against tsunami of the same magnitude of 1983 East Sea Tsunami

Site selection for nuclear power plants and geologic seismologia influence

International Nuclear Information System (INIS)

Castro Feitosa, G. de.

1985-01-01

The site selection for nuclear power plants is analised concerning to the process, methodology and the phases in an overall project efforts. The factors affecting are analised on a general viewpoint, showing the considerations given to every one. The geologic and seismologic factors influence on the foundation design are more detailed analised, with required investigation and procedures accordingly sub-soil conditions in the site [pt

Addendum to engineering evaluation/cost analysis for the proposed management of 15 nonprocess buildings (15 Series) at the Weldon Spring site chemical plant, Weldon Spring, Missouri

International Nuclear Information System (INIS)

MacDonell, M.M.; Peterson, J.M.

1990-08-01

An engineering evaluation/cost analysis (EE/CA) report was prepared in May 1989 to analyze alternatives for a proposed removal action to manage 15 nonprocess buildings, designated as the 15 Series buildings, at the chemical plant area of the Weldon Spring site. The alternative selected as a result of the analyses was to dismantle the buildings and to salvage or transport off-site for treatment or disposal all nonradioactively contaminated materials and to store on-site in a material staging area (MSA) all radioactively contaminated materials, pending a decision for disposal of all wastes resulting from remediation of the Weldon Spring site. Region VII of the US Environmental Protection Agency (EPA) and the state of Missouri concurred with the selection of this alternative and provided comments on the EE/CA report. The proposed removal action was not initiated at that time due to funding constraints. This addendum has been prepared to update information provided in the EE/CA report, provide additional information on the MSA, and respond to EPA Region VII and state of Missouri comments on the EE/CA. 5 refs., 1 tab

Cooling water in the study of nuclear power plants sites

International Nuclear Information System (INIS)

Martinez, J.J.C.

1990-01-01

The location of an electric power plant has its limitations as regards the availability of apt sites. The radiosanitary risk, seismic risk and the overload capacity of the ground can be generically enumerated, being the cooling water availability for an electric power plant a basic requirement. Diverse cooling systems may be employed but the aim must always be that thermal contamination in the immediate environment be the least possible. (Author) [es

Quality assurance during site construction of nuclear power plants

International Nuclear Information System (INIS)

1981-01-01

This Safety Guide provides requirements and recommendations related to the establishment and implementation of a quality assurance programme for the site construction activities at nuclear power plants. These include activities such as fabricating, erecting, installing, handling, storing, cleaning, flushing, inspecting, testing, modifying, repairing, and maintaining

Siting Conflicts in Renewable Energy Projects in Sweden: Experiences From the Siting of a Biogas Plant

Energy Technology Data Exchange (ETDEWEB)

Khan, Jamil

2001-05-01

This paper seeks to contribute to an increased understanding of what characterises conflicts regarding the siting of renewable energy facilities. The paper starts out with a brief introduction to different types of renewable energy and the conflicts they might generate as well as a discussion about the differences and similarities in comparison with conflicts over more controversial issues, such as nuclear plants, chemical factories and the construction of roads. The main part of the paper discusses the results from a case study on a failed attempt to site a biogas plant in southern Sweden. The results show that there was a lack of public participation in the early stages of planning, and that peoples negative perceptions of the possibilities to influence the decision-making and of the attitude of the developer, contributed to the development of a public opposition and a polarisation of the conflict. There is also a discussion about the reasons for a shift in the political support for the project and about the role of the legislation in shaping planning processes that either handle conflicts or make them worse. The paper concludes with the observation that the biogas case, in many ways, resembled traditional siting conflicts and that further research is needed to explore the nature of different renewable energy siting conflicts.

Plants from the abandoned Nacozari mine tailings: evaluation of their phytostabilization potential

Directory of Open Access Journals (Sweden)

Alina E. Santos

2017-05-01

Full Text Available Phytostabilization is a remediation technology that uses plants for in-situ stabilization of contamination in soils and mine tailings. The objective of this study was to identify native plant species with potential for phytostabilization of the abandoned mine tailings in Nacozari, Sonora in northern Mexico. A flora of 42 species in 16 families of angiosperms was recorded on the tailings site and the abundance of the most common perennial species was estimated. Four of the five abundant perennial species showed evidence of regeneration: the ability to reproduce and establish new seedlings. A comparison of selected physicochemical properties of the tailings in vegetated patches with adjacent barren areas suggests that pH, electrical conductivity, texture, and concentration of potentially toxic elements do not limit plant distribution. For the most abundant species, the accumulation factor for most metals was <1, with the exception of Zn in two species. A short-term experiment on adaptation revealed limited evidence for the formation of local ecotypes in Prosopis velutina and Amaranthus watsonii. Overall, the results of this study indicate that five native plant species might have potential for phytostabilization of the Nacozari tailings and that seed could be collected locally to revegetate the site. More broadly, this study provides a methodology that can be used to identify native plants and evaluate their phytostabilization potential for similar mine tailings.

Waste Isolation Pilot Plant site environmental report, for calendar year 1995

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-09-01

The U.S. Department of Energy (DOE) Order 5400.1 General Environmental Protection Program, requires DOE facilities, that conduct environmental protection programs, to annually prepare a Site Environmental Report (SER). The purpose of the SER is to provide an abstract of environmental assessments conducted in order to characterize site environmental management performance, to confirm compliance with environmental standards and requirements, and to highlight significant programs and efforts of environmental merit. The content of this SER is not restricted to a synopsis of the required data, in addition, information pertaining to new and continued monitoring and compliance activities during the 1995 calendar year are also included. Data contained in this report are derived from those monitoring programs directed by the Waste Isolation Pilot Plant (WIPP) Environmental Monitoring Plan (EMP). The EMP provides inclusive guidelines implemented to detect potential impacts to the environment and to establish baseline measurements for future environmental evaluations. Surface water, groundwater. air, soil, and biotic matrices are monitored for an array of radiological and nonradiological factors. The baseline radiological surveillance program encompasses a broader geographic area that includes nearby ranches, villages, and cities. Most elements of nonradiological assessments are conducted within the geographic vicinity of the WIPP site.

Waste Isolation Pilot Plant site environmental report, for calendar year 1995

International Nuclear Information System (INIS)

1996-01-01

The U.S. Department of Energy (DOE) Order 5400.1 General Environmental Protection Program, requires DOE facilities, that conduct environmental protection programs, to annually prepare a Site Environmental Report (SER). The purpose of the SER is to provide an abstract of environmental assessments conducted in order to characterize site environmental management performance, to confirm compliance with environmental standards and requirements, and to highlight significant programs and efforts of environmental merit. The content of this SER is not restricted to a synopsis of the required data, in addition, information pertaining to new and continued monitoring and compliance activities during the 1995 calendar year are also included. Data contained in this report are derived from those monitoring programs directed by the Waste Isolation Pilot Plant (WIPP) Environmental Monitoring Plan (EMP). The EMP provides inclusive guidelines implemented to detect potential impacts to the environment and to establish baseline measurements for future environmental evaluations. Surface water, groundwater. air, soil, and biotic matrices are monitored for an array of radiological and nonradiological factors. The baseline radiological surveillance program encompasses a broader geographic area that includes nearby ranches, villages, and cities. Most elements of nonradiological assessments are conducted within the geographic vicinity of the WIPP site

Investigation and feasibility study of a former manufactured gas plant site in Tuttlingen (Germany), based on individually determined clean-up criteria

Energy Technology Data Exchange (ETDEWEB)

Heinecker, C.; Pickel, H.-J.; Duffek, J. [HPC Harress Pickel Consult GmbH, Fuldatal (Germany)

1995-12-31

At the request of the former plant operator, a manufactured gas plant site in Tuttlingen, Germany, was investigated from 1988 through 1992 for subsurface soil contamination resulting from former activities. In 1991, the contents of the former tar pits and parts of the adjacent soil contaminations were removed in the course of clean-up activities by means of excavation and disposed at a special waste site. Following an initial risk assessment, a remedial investigation was carried out in order to further delineate the contaminated areas as well as to create a reliable database for a feasibility study of remedial alternatives. The feasibility study followed applicable Baden-Wurttemberg state guidelines, including the following elements: Determination of the clean-up goals for soils; pre-selection of the clean-up procedure; cost estimate; cost-effectiveness study; Non-monetary evaluation; and total evaluation/clean-up proposal. The following general alternatives were available for the definition of clean-up goals: background values (`H-values`); general guidelines values (`SZ-values`); and clean-up goals based on contaminant fate and transport as well as site use (`SZA-values`).

Safety Considerations in the Selection of Nuclear Power Plant Candidate Sites in Johor State, Malaysia

International Nuclear Information System (INIS)

Ramli, A.T.; Basri, N.A.; Abu Hanifah, N.Z.H.

2014-01-01

Nuclear power is considered as one of the best options for future energy development in Malaysia. Since Malaysia has no experience in nuclear energy generation / production, commissioning the first nuclear power plant needs tremendous effort in various aspects. The most obvious challenges are to ensure the nation’s safety and to handle security issues that may arise from a nuclear power plant site. This paper aims to propose a site for nuclear power plant in Johor State, Malaysia as well as listing the possible safety challenges in the process. The site selection uses the Malaysian Atomic Energy Licensing Board (AELB) guideline document as the main reference, supported by documents from International Atomic Energy Agency (IAEA) and from various countries. Only five site characteristics are chosen as study parameters – geological features and seismic data, air dispersion analysis using meteorological data, population distribution, safety zones and emergency supports. This paper concluded that site number 2 (CS2) at Tanjung Tenggaroh, Mersing is the most suitable area for nuclear power plant in Johor state. It has the least possible risks, safety and security issues. (author)

Safety Considerations in the Selection of Nuclear Power Plant Candidate Sites in Johor State, Malaysia

Energy Technology Data Exchange (ETDEWEB)

Ramli, A. T.; Basri, N. A.; Abu Hanifah, N. Z.H., [Department of Physics, Faculty of Science Universiti Teknologi Malaysia Johor (Malaysia)

2014-10-15

Nuclear power is considered as one of the best options for future energy development in Malaysia. Since Malaysia has no experience in nuclear energy generation / production, commissioning the first nuclear power plant needs tremendous effort in various aspects. The most obvious challenges are to ensure the nation’s safety and to handle security issues that may arise from a nuclear power plant site. This paper aims to propose a site for nuclear power plant in Johor State, Malaysia as well as listing the possible safety challenges in the process. The site selection uses the Malaysian Atomic Energy Licensing Board (AELB) guideline document as the main reference, supported by documents from International Atomic Energy Agency (IAEA) and from various countries. Only five site characteristics are chosen as study parameters – geological features and seismic data, air dispersion analysis using meteorological data, population distribution, safety zones and emergency supports. This paper concluded that site number 2 (CS2) at Tanjung Tenggaroh, Mersing is the most suitable area for nuclear power plant in Johor state. It has the least possible risks, safety and security issues. (author)

Comparison of the incidence of Listeria on equipment versus environmental sites within dairy processing plants.

Science.gov (United States)

Pritchard, T J; Flanders, K J; Donnelly, C W

1995-08-01

This study was undertaken to compare the incidence of Listeria contamination of processing equipment with that of the general dairy processing environment. A total of 378 sponge samples obtained from 21 dairy plants were analyzed for Listeria using three different enrichment media. Use of extended microbiological analysis allowed us to identify 26 Listeria positive sites which would have not been identified had a single test format been employed. Eighty (80) of 378 sites (21.2%) were identified as Listeria positive. Listeria innocua was isolated from 59 of the 80 (73.8%) positive samples, L. monocytogenes was identified in 35 (43.8%) of the positive samples, and L. seeligeri was isolated from 5 (6.3%) of the Listeria positive samples. Positive equipment samples were obtained from 6 of the 21 (28.6%) plants and 19 of the 21 (90.5%) plants had positive environmental sites. Seventeen of the 215 (7.9%) samples from equipment were positive for Listeria species. Eleven of these sites, including 3 holding tanks, 2 table tops, 3 conveyor/chain systems, a pasta filata wheel, a pint milk filler and a brine pre-filter machine, were positive for L. monocytogenes. Nineteen of the 21 (90.5%) plants had positive environmental sites. Sixty-three of the 163 (41.1%) samples from environmental sites were Listeria positive and 24 were positive for L. monocytogenes. Two-tailed student t-test analysis of the mean frequencies indicated that the level of contamination was significantly higher (p plant, and that greater emphasis needs to be placed on the cleaning and sanitizing of the plant environment.

Dose evaluation for the public around the Tokai reprocessing plant

International Nuclear Information System (INIS)

Takeishi, Minoru; Furuta, Sadaaki; Miyabe, Kenjiro; Shinohara, Kunihiko

2007-01-01

The dose evaluations for the public around the Tokai Reprocessing Plant (TRP) have been carried out by using the mathematical models, because the effects on the environmental radiation due to the operation of the TRP are too small to separate from the background level. The models were developed by the site-specific investigations of the environment and reviewed in several times based on the latest scientific knowledge. The maximum annual effective dose through the whole period of the operation of the TRP was evaluated as 1.4 μSv with the data of the discharge monitoring and the meteorological observation in 1992. The evaluated doses revealed to be kept as far below the annual dose limit for the public as 1 mSv. (author)

Climatology of the Savannah River Plant site

International Nuclear Information System (INIS)

Hoel, D.D.

1983-01-01

This document is intended as a reference for those involved in environmental research, and preparing environmental and safety analysis reports about aspects of operations of production and support facilities at the Savannah River Plant (SRP). The information in this document is drawn from appropriate references and from the extensive meteorological data base collected on SRP. This document contains information on the climatological characteristics of the SRP site, as well as information on relative concentrations and deposition for specific radionuclides

A method for site-dependent planning and its application to the preselection of sites for thermal power plants

International Nuclear Information System (INIS)

Friedrich, R.

1979-01-01

In the first part of the paper a computer-aided method for dealing with the problems of site-dependent planning is described. By means of the modular program system COPLAN complex conjunction between locally varying data can be performed rapidly and accurately with respect to spatial orientation. The system consists of data input, numerous ways of processing, and graphical representation of the results. The second part shows the application of the system to preselection of sites for thermal power plants. By means of a method analyzing its usefulness, the suitability of each point in (the German Federal State of) Baden-Wuerttemberg as a power plant site is determined. Compared with the currently used methods of preliminary site selection the present method is distinguished by area-covering calculation, the possibility of balancing up advantages and disadvantages, as well as transparency and suitability for being checked up. The paper establishes and considers criteria from the fields of operational economy, safety, ecology, and district planning. The computations are performed for different orders of preference. It is shown that there are regions of sites which are acceptable with respect to a large spectrum of object systems. (orig.) [de

Regulatory inspection activities on nuclear power plant sites during construction in the United Kingdom

International Nuclear Information System (INIS)

Jeffery, J.V.

1977-01-01

The work of regulatory inspection of the construction of the plant on the site is performed not only by the inspector who has been allocated to inspection duties for that site but also by the specialist staff who are involved with the safety assessment of the plant. The co-ordination of this work is described in the paper and examples are given of inspection activities associated with the enforcement requirements of licence conditions as well as those related to the inspection of the plant itself. (author)

Radiation burden of population in nuclear power plant siting

International Nuclear Information System (INIS)

Navratil, J.

The significance is discussed of the determination of the radiobiological consequences of normal operation and design basis accidents in nuclear power plant siting. The basic diagram and brief description is given of the programme for calculating the radiation load of the population in the surroundings of the nuclear power plant. The programme consists of two subprogrammes, i.e., the dispersion of radioactive gases (for normal operation and for accidents), the main programme for the determination of biological consequences and one auxiliary programme (the distribution of the population in the surroundings of the power plant). The four most important types of exposure to ionizing radiation are considered, namely inhalation, external irradiation from a cloud, ingestion (water, milk, vegetables), external irradiation from the deposit. (B.S.)

Waste Isolation Pilot Plant Site Environmental Report Calendar Year 2002

Energy Technology Data Exchange (ETDEWEB)

Washington Regulatory and Environmental Services

2003-09-17

The United States (U.S.) Department of Energy (DOE) Carlsbad Field Office (CBFO) and Washington TRU Solutions LLC (WTS) are dedicated to maintaining high quality management of Waste Isolation Pilot Plant (WIPP) environmental resources. DOE Order 5400.1, General Environmental Protection Program, and DOE Order 231.1, Environment, Safety, and Health Reporting, require that the environment at and near DOE facilities be monitored to ensure the safety and health of the public and the environment. This Waste Isolation Pilot Plant 2002 Site Environmental Report summarizes environmental data from calendar year 2002 that characterize environmental management performance and demonstrate compliance with federal and state regulations. This report was prepared in accordance with DOE Order 5400.1, DOE Order 231.1, and Guidance for the Preparation of DOE Annual Site Environmental Reports (ASERs) for Calendar Year 2002 (DOE Memorandum EH-41: Natoli:6-1336, April 4, 2003). These Orders and the guidance document require that DOE facilities submit an annual site environmental report to DOE Headquarters, Office of the Assistant Secretary for Environment, Safety, and Health; and the New Mexico Environment Department (NMED).

Waste Isolation Pilot Plant Site Environmental Report Calendar Year 2002

International Nuclear Information System (INIS)

Washington Regulatory and Environmental Services

2003-01-01

The United States (U.S.) Department of Energy (DOE) Carlsbad Field Office (CBFO) and Washington TRU Solutions LLC (WTS) are dedicated to maintaining high quality management of Waste Isolation Pilot Plant (WIPP) environmental resources. DOE Order 5400.1, General Environmental Protection Program, and DOE Order 231.1, Environment, Safety, and Health Reporting, require that the environment at and near DOE facilities be monitored to ensure the safety and health of the public and the environment. This Waste Isolation Pilot Plant 2002 Site Environmental Report summarizes environmental data from calendar year 2002 that characterize environmental management performance and demonstrate compliance with federal and state regulations. This report was prepared in accordance with DOE Order 5400.1, DOE Order 231.1, and Guidance for the Preparation of DOE Annual Site Environmental Reports (ASERs) for Calendar Year 2002 (DOE Memorandum EH-41: Natoli:6-1336, April 4, 2003). These Orders and the guidance document require that DOE facilities submit an annual site environmental report to DOE Headquarters, Office of the Assistant Secretary for Environment, Safety, and Health; and the New Mexico Environment Department (NMED)

Environmental site description for a Uranium Atomic Vapor Laser Isotope Separation (U-AVLIS) production plant at the Paducah Gaseous Diffusion Plant site

International Nuclear Information System (INIS)

Marmer, G.J.; Dunn, C.P.; Moeller, K.L.; Pfingston, J.M.; Policastro, A.J.; Yuen, C.R.; Cleland, J.H.

1991-09-01

Uranium enrichment in the United States has utilized a diffusion process to preferentially enrich the U-235 isotope in the uranium product. The U-AVLIS process is based on electrostatic extraction of photoionized U-235 atoms from an atomic vapor stream created by electron-beam vaporization of uranium metal alloy. The U-235 atoms are ionized when precisely tuned laser light -- of appropriate power, spectral, and temporal characteristics -- illuminates the uranium vapor and selectively photoionizes the U-235 isotope. A programmatic document for use in screening DOE site to locate a U-AVLIS production plant was developed and implemented in two parts. The first part consisted of a series of screening analyses, based on exclusionary and other criteria, that identified a reasonable number of candidate sites. These sites were subjected to a more rigorous and detailed comparative analysis for the purpose of developing a short list of reasonable alternative sites for later environmental examination. This environmental site description (ESD) provides a detailed description of the PGDP site and vicinity suitable for use in an environmental impact statement (EIS). The report is based on existing literature, data collected at the site, and information collected by Argonne National Laboratory (ANL) staff during a site visit. 65 refs., 15 tabs

Environmental site description for a Uranium Atomic Vapor Laser Isotope Separation (U-AVLIS) production plant at the Paducah Gaseous Diffusion Plant site

Energy Technology Data Exchange (ETDEWEB)

Marmer, G.J.; Dunn, C.P.; Moeller, K.L.; Pfingston, J.M.; Policastro, A.J.; Yuen, C.R.; Cleland, J.H. (ed.)

1991-09-01

Uranium enrichment in the United States has utilized a diffusion process to preferentially enrich the U-235 isotope in the uranium product. The U-AVLIS process is based on electrostatic extraction of photoionized U-235 atoms from an atomic vapor stream created by electron-beam vaporization of uranium metal alloy. The U-235 atoms are ionized when precisely tuned laser light -- of appropriate power, spectral, and temporal characteristics -- illuminates the uranium vapor and selectively photoionizes the U-235 isotope. A programmatic document for use in screening DOE site to locate a U-AVLIS production plant was developed and implemented in two parts. The first part consisted of a series of screening analyses, based on exclusionary and other criteria, that identified a reasonable number of candidate sites. These sites were subjected to a more rigorous and detailed comparative analysis for the purpose of developing a short list of reasonable alternative sites for later environmental examination. This environmental site description (ESD) provides a detailed description of the PGDP site and vicinity suitable for use in an environmental impact statement (EIS). The report is based on existing literature, data collected at the site, and information collected by Argonne National Laboratory (ANL) staff during a site visit. 65 refs., 15 tabs.

Food surveys for assessing chemical and dosimetric impacts near industrial sites; Enquetes alimentaires pour l'evaluation des impacts chimiques et dosimetriques a proximite de sites nucleaires

Energy Technology Data Exchange (ETDEWEB)

Parache, V.; Maurau, S.; Mercat, C.

2011-03-15

Estimating the ingestion of potentially contaminated foodstuffs around conventional and nuclear industrial sites requires data about the food practices and eating habits of the local residents, especially the consumption of locally- and home-produced food. The IRSN thus chose to conduct surveys about these practices in the vicinity of nuclear sites. Their methodology was based on previous surveys near nuclear sites. In 2004, in partnership with AREVA and BEGEAT, the French Institute for Radioprotection and Nuclear Safety studied the eating habits of the residents of Bollene, near the Tricastin plant (Rhone Valley), with the aim of improving the quantification of the plant's potential health impacts. Based on these studies and as part of the SENSIB project to characterize vulnerability to nuclear risks, we developed and tested a survey protocol during the summer 2008, around the Chinon nuclear plant, in collaboration with EDF. The protocol is currently being tested around the Marcoule nuclear plant, in collaboration with the CEA. The aim was to optimize the feasibility and the reproducibility of the approach, while losing none of the robustness of the results. The data obtained made it possible to evaluate daily food intake values for individuals and to assess the rates of consumption of locally-grown products for many food categories. The data showed the existence of local population groups with very high rates of locally-grown food consumption - over 90 % of certain food products. This comparative study thus shows the significant variability of eating habits in the French population and proposes a reproducible approach to evaluating realistic indicators of potentially risky dietary habits. (authors)

A pragmatic pairwise group-decision method for selection of sites for nuclear power plants

International Nuclear Information System (INIS)

Kutbi, I.I.

1987-01-01

A pragmatic pairwise group-decision approach is applied to compare two regions in order to select the more suitable one for construction of nulcear power plants in the Kingdom of Saudi Arabia. The selection methodology is based on pairwise comparison by forced choice. The method facilitates rating of the regions or sites using simple calculations. Two regions, one close to Dhahran on the Arabian Gulf and another close to Jeddah on the Red Sea, are evaluated. No specific site in either region is considered at this stage. The comparison is based on a set of selection criteria which include (i) topography, (ii) geology, (iii) seismology, (iv) meteorology, (v) oceanography, (vi) hydrology and (vii) proximetry to oil and gas fields. The comparison shows that the Jeddah region is more suitable than the Dhahran region. (orig.)

The Homecourt coke plant site: a successful redeveloped brown field case

International Nuclear Information System (INIS)

Charbonnier, P.; Piguet, O.; Lereboullet, L.

2006-01-01

The environmental diagnosis of the coke plant site in Homecourt has been carried out over the last 15 years. Bail Industrie has selected two zones on the site for a remediation program in view of their further redevelopment. The weakly polluted grounds were submitted to a bio treatment, while the more polluted grounds were treated by thermal desorption. Tars have been incinerated off site. To assess the effectiveness of the treatment, percolation tests are carried out. (authors)

SITE-2, Power Plant Siting, Cost, Environment, Seismic and Meteorological Effects

International Nuclear Information System (INIS)

Frigerio, N.A.; Habegger, L.J.; King, R.F.; Hoover, L.J.; Clark, N.A.; Cobian, J.M.

1977-01-01

1 - Description of problem or function: SITE2 is designed to (1) screen candidate energy facility sites or areas within an electric utility region, based on the region's physical and socioeconomic attributes, the planned facility's characteristics, and impact assessments, and (2) evaluate the cumulative regional impacts associated with alternate energy supply options and inter-regional energy import/export practices, specifically, comparison of different energy technologies and their regional distribution in clustered or dispersed patterns. 2 - Method of solution: The SITE2 methodology is based on the quantification of three major site-related vectors. A cost vector is determined which identifies site-specific costs, such as transmission costs, cooling costs as related to water availability, and costs of specific controls needed to protect the surrounding environment. An impact vector is also computed for each potential site, using models of health and environmental impacts incurred in areas adjacent to the site. Finally, a site attribute vector is developed which reflects such characteristics as population, seismic conditions, meteorology, land use, and local ecological systems. This vector can be used to eliminate certain sites because of their inability to satisfy specific constraints. These three vectors can be displayed as density maps and combined in a simple overlay approach, similar to that developed by I. L. McHarg in reference 2, to identify candidate sites. Alternatively, the vector elements can be computationally combined into a weighted sum to obtain quantitative indicators of site suitability

SITE-2, Power Plant Siting, Cost, Environment, Seismic and Meteorological Effects

Energy Technology Data Exchange (ETDEWEB)

Frigerio, N A [Environmental Impact Studies, Argonne National Laboratory 9700 South Cass Avenue, Argonne, Illinois 60439 (United States); Habegger, L J; King, R F; Hoover, L J [Energy and Environmental Systems Division, Argonne National Laboratory 9700 South Cass Avenue, Argonne, Illinois 60439 (United States); Clark, N A [Applied Mathematics Division, Argonne National Laboratory, 9700 South Cass Avenue, Argonne, Illinois 60439 (United States); Cobian, J M [Northwestern University, Evanston, Illinois 60201 (United States)

1977-08-01

1 - Description of problem or function: SITE2 is designed to (1) screen candidate energy facility sites or areas within an electric utility region, based on the region's physical and socioeconomic attributes, the planned facility's characteristics, and impact assessments, and (2) evaluate the cumulative regional impacts associated with alternate energy supply options and inter-regional energy import/export practices, specifically, comparison of different energy technologies and their regional distribution in clustered or dispersed patterns. 2 - Method of solution: The SITE2 methodology is based on the quantification of three major site-related vectors. A cost vector is determined which identifies site-specific costs, such as transmission costs, cooling costs as related to water availability, and costs of specific controls needed to protect the surrounding environment. An impact vector is also computed for each potential site, using models of health and environmental impacts incurred in areas adjacent to the site. Finally, a site attribute vector is developed which reflects such characteristics as population, seismic conditions, meteorology, land use, and local ecological systems. This vector can be used to eliminate certain sites because of their inability to satisfy specific constraints. These three vectors can be displayed as density maps and combined in a simple overlay approach, similar to that developed by I. L. McHarg in reference 2, to identify candidate sites. Alternatively, the vector elements can be computationally combined into a weighted sum to obtain quantitative indicators of site suitability.

Seismic re-evaluation of piping systems of heavy water plant, Kota

International Nuclear Information System (INIS)

Mishra, Rajesh; Soni, R.S.; Kushwaha, H.S.; Venkat Raj, V.

2002-05-01

Heavy Water Plant, Kota is the first indigenous heavy water plant built in India. The plant started operation in the year 1985 and it is approaching the completion of its originally stipulated design life. In view of the excellent record of plant operation for the past so many years, it has been planned to carry out various exercises for the life extension of the plant. In the first stage, evaluation of operation stresses was carried out for the process critical piping layouts and equipment, which are connected with 25 process critical nozzle locations, identified based on past history of the plant performance. Fatigue life evaluation has been carried out to fmd out the Cumulative Usage Factor, which helps in arriving at a decision regarding the life extension of the plant. The results of these exercises have been already reported separately vide BARC/200I /E/O04. In the second stage, seismic reevaluation of the plant has been carried out to assess its ability to maintain its integ:rity in case of a seismic event. The aim of this exercise is to assess the effects of the maximum probable earthquake at the plant site on the various systems and components of the plant. This exercise is further aimed at ensuring the adequacy of seismic supports to maintain the integrity of the system in case of a seismic event and to suggest some retrofitting measures, if required. Seismic re-evaluation of the piping of Heavy Water Plant, Kota has been performed taking into account the interaction effects from the connected equipment. Each layout has been qualified using the latest provisions of ASME Code Section III, Subsection ND wherein the earthquake loading has been considered as a reversing dynamic load. The maximum combined stresses for all the layouts due to pressure, weight and seismic loadings have been found to be well within the code allowable limit. Therefore, it has been concluded that during a maximum probable seismic event, the possibility of pipe rupture can be safely

Evaluation and Numerical Simulation of Tsunami for Coastal Nuclear Power Plants of India

International Nuclear Information System (INIS)

Sharma, Pavan K.; Singh, R.K.; Ghosh, A.K.; Kushwaha, H.S.

2006-01-01

Recent tsunami generated on December 26, 2004 due to Sumatra earthquake of magnitude 9.3 resulted in inundation at the various coastal sites of India. The site selection and design of Indian nuclear power plants demand the evaluation of run up and the structural barriers for the coastal plants: Besides it is also desirable to evaluate the early warning system for tsunami-genic earthquakes. The tsunamis originate from submarine faults, underwater volcanic activities, sub-aerial landslides impinging on the sea and submarine landslides. In case of a submarine earthquake-induced tsunami the wave is generated in the fluid domain due to displacement of the seabed. There are three phases of tsunami: generation, propagation, and run-up. Reactor Safety Division (RSD) of Bhabha Atomic Research Centre (BARC), Trombay has initiated computational simulation for all the three phases of tsunami source generation, its propagation and finally run up evaluation for the protection of public life, property and various industrial infrastructures located on the coastal regions of India. These studies could be effectively utilized for design and implementation of early warning system for coastal region of the country apart from catering to the needs of Indian nuclear installations. This paper presents some results of tsunami waves based on different analytical/numerical approaches with shallow water wave theory. (authors)

Adaptive Management Plan for Sensitive Plant Species on the Nevada Test Site

International Nuclear Information System (INIS)

Wills, C. A.

2001-01-01

The Nevada Test Site supports numerous plant species considered sensitive because of their past or present status under the Endangered Species Act and with federal and state agencies. In 1998, the U.S. Department of Energy, Nevada Operation Office (DOE/NV) prepared a Resource Management Plan which commits to protects and conserve these sensitive plant species and to minimize accumulative impacts to them. This document presents the procedures of a long-term adaptive management plan which is meant to ensure that these goals are met. It identifies the parameters that are measured for all sensitive plant populations during long-term monitoring and the adaptive management actions which may be taken if significant threats to these populations are detected. This plan does not, however, identify the current list of sensitive plant species know to occur on the Nevada Test Site. The current species list and progress on their monitoring is reported annually by DOE/NV in the Resource Management Plan

Estimating release of polycyclic aromatic hydrocarbons from coal-tar contaminated soil at manufactured gas plant sites. Final report

International Nuclear Information System (INIS)

Lee, L.S.

1998-04-01

One of EPRI's goals regarding the environmental behavior of organic substances consists of developing information and predictive tools to estimate the release potential of polycyclic aromatic hydrocarbons (PAHs) from contaminated soils at manufactured gas (MGP) plant sites. A proper assessment of the distribution of contaminants under equilibrium conditions and the potential for mass-transfer constraints is essential in evaluating the environmental risks of contaminants in the subsurface at MGP sites and for selecting remediation options. The results of this research provide insights into estimating maximum release concentrations of PAHs from MGP soils that have been contaminated by direct contact with the tar or through years of contact with contaminated groundwater. Attention is also given to evaluating the use of water-miscible cosolvents for estimating aqueous phase concentrations, and assessing the role of mass-transfer constraints in the release of PAHs from MGP site soils

Plant species from coal mine overburden dumping site in Satui, South Kalimantan, Indonesia

Directory of Open Access Journals (Sweden)

Vivi Novianti

2017-07-01

Full Text Available Coal mine overburden (OB materials were nutrient-poor, loosely adhered particles of shale, stones, boulders, and cobbles, also contained elevated concentration of trace metals. This condition cause OB substrate did not support plants growth. However, there were certain species that able to grow on overburden dumping site. This investigation sought to identify plants species that presence on coal mine overburden. The research was conducted on opencast coal mine OB dumping site in Satui, South Kalimantan. Vegetation sampling was carried out on six different ages of coal mine OB dumps (7, 10, 11, 42, 59 and 64 month using line transect. Species identification used information from local people, AMDAL report of PT Arutmin Indonesia-Satui mine project, and website. There were 123 plant species, consisted of 79 herbs (Cyperaceae, Poaceae and Asteraceae, 10 lianes, bryophyte, 9 ferns, 10 shrubs, and 14 trees. A number of Poaceae, i.e., Paspalumconjugatum, Paspalumdilatatum, and Echinochloacolona generally present among the stones, boulders, and cobbles. While Cyperaceae such as Fimbristylis miliaceae, Cyperus javanicus, Rhyncospora corymbosa and Scleria sumatrensis most often foundinand around thebasin/pond with its smooth and humid substrate characteristics. Certain species of shrubs and trees present on the 7 month OB dumping site. They wereChromolaena odorata, Clibadium surinamense, Melastoma malabathricum, Trema micrantha, and Solanum torvum (Shrubs, Ochroma pyramidale and Homalanthus populifolius (trees. This plant species could be used for accelerating primary succession purpose on coal mine overburden dumping site. Nevertheless, species selection was needed to avoid planting invasive species.

Study of seismic design bases and site conditions for nuclear power plants

International Nuclear Information System (INIS)

1980-04-01

This report presents the results of an investigation of four topics pertinent to the seismic design of nuclear power plants: Design accelerations by regions of the continental United States; review and compilation of design-basis seismic levels and soil conditions for existing nuclear power plants; regional distribution of shear wave velocity of foundation materials at nuclear power plant sites; and technical review of surface-founded seismic analysis versus embedded approaches

Study of seismic design bases and site conditions for nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

1980-04-01

This report presents the results of an investigation of four topics pertinent to the seismic design of nuclear power plants: Design accelerations by regions of the continental United States; review and compilation of design-basis seismic levels and soil conditions for existing nuclear power plants; regional distribution of shear wave velocity of foundation materials at nuclear power plant sites; and technical review of surface-founded seismic analysis versus embedded approaches.

300 Area steam plant replacement, Hanford Site, Richland, Washington: Environmental assessment

International Nuclear Information System (INIS)

1997-03-01

Steam to support process operations and facility heating is currently produced by a centralized oil-fired plant located in the 300 Area and piped to approximately 26 facilities in the 300 Area. This plant was constructed during the 1940s and, because of tis age, is not efficient, requires a relatively large operating and maintenance staff, and is not reliable. The US Department of Energy is proposing an energy conservation measure for a number of buildings in the 300 Area of the Hanford Site. This action includes replacing the centralized heating system with heating units for individual buildings or groups of buildings, constructing new natural gas pipelines to provide a fuel source for many of these units and constructing a central control building to operate and maintain the system. A new steel-sided building would be constructed in the 300 Area in a previously disturbed area at least 400 m (one-quarter mile) from the Columbia River, or an existing 300 Area building would be modified and used. This Environmental Assessment evaluates alternatives to the proposed actions. Alternatives considered are: (1) the no action alternative; (2) use of alternative fuels, such as low-sulfur diesel oil; (3) construction of a new central steam plant, piping and ancillary systems; (4) upgrade of the existing central steam plant and ancillary systems; and (5) alternative routing of the gas distribution pipeline that is a part of the proposed action. A biological survey and culture resource review and survey were also conducted

Evaluation of breastfeeding Web sites for patient education.

Science.gov (United States)

Dornan, Barbara A; Oermann, Marilyn H

2006-01-01

To evaluate the quality of Web sites on breastfeeding for patient education. Descriptive study of 30 Web sites on breastfeeding for patient education, evaluated based on the Health Information Technology Institute (HITI) criteria, readability, and eight content criteria from the American Academy of Pediatrics (AAP) policy statement on breastfeeding. The mean Flesch-Kincaid Grade Level for readability of the 30 sites was 9.2. Seven of the sites included all eight of the content criteria from the AAP, and three sites did not include any of the information recommended by the AAP content criteria. Nurses should be able to recommend best patient education materials for their patients. The five best Web sites for breastfeeding education are identified for patient teaching, and the HITI criteria are explained for nurses to learn how to evaluate Web sites for themselves and their patients.

Subcellular site and nature of intracellular cadmium in plants

International Nuclear Information System (INIS)

Wagner, G.J.

1979-01-01

The mechanisms underlying heavy metal accumulation, toxicity and tolerance in higher plants are poorly understood. Since subcellular processes are undoubtedly involved in all these phenomena, it is of interest to study the extent of, subcellular site of and nature of intracellularly accumulated cadmium in higher plants. Whole plants supplied 109 CdCl 2 or 112 CdSO 4 accumulated Cd into roots and aerial tissues. Preparation of protoplasts from aerial tissue followed by subcellular fractionation of the protoplasts to obtain intact vacuoles, chloroplasts and cytosol revealed the presence of Cd in the cytosol but not in vacuoles or chloroplasts. Particulate materials containing other cell components were also labeled. Of the 109 Cd supplied to plants, 2 to 10% was recovered in both cytosol preparations and in particulate materials. Cytosol contained proteinaceous--Cd complexes, free metal and low molecular weight Cd complexes. Labeling of protoplasts gave similar results. No evidence was obtained for the production of volatile Cd complexes in tobacco

Habitat types on the Hanford Site: Wildlife and plant species of concern

Energy Technology Data Exchange (ETDEWEB)

Downs, J.L.; Rickard, W.H.; Brandt, C.A. [and others

1993-12-01

The objective of this report is to provide a comprehensive source of the best available information on Hanford Site sensitive and critical habitats and plants and animals of importance or special status. In this report, sensitive habitats include areas known to be used by threatened, endangered, or sensitive plant or animal species, wetlands, preserves and refuges, and other sensitive habitats outlined in the Hanford Site Baseline Risk Assessment Methodology. Potentially important species for risk assessment and species of special concern with regard to their status as threatened, endangered, or sensitive are described, and potential habitats for these species identified.

Selection of sites for nuclear power plants in The Netherlands. Pt. B

International Nuclear Information System (INIS)

1986-01-01

In this report the headlines are presented of the participation of the Dutch people in the policy resolution with regard to the selection of sites of nuclear power plants. In Ch. 1 it is indicated how this participation is organized and the quantitative results are given. In the other chapters the results of the people's participation are treated qualitatively with restriction to the headlines. In Ch. 3 the remarks about the procedure and its precedents are reported. Ch. 4 reflects the public opinion with regard to the (nuclear) energy problem. In Ch. 5 finally the problems concerning the sites of nuclear power plants are treated. The criteria are discussed used by the participants in the judgement of the locations on their aptitude, in general as well as by possible site. (Auth.)

Site Release Report for C-Well Pipeline, UE-25 Large Rocks Test Site, and 29 GSF Test Pits

International Nuclear Information System (INIS)

K.E. Rasmuson

2002-01-01

The U.S. Department of Energy has implemented a program to reclaim lands disturbed by site characterization at Yucca Mountain. Long term goals of the program are to re-establish processes on disturbed sites that will lead to self-sustaining plant communities. The Biological Opinion for Yucca Mountain Site Characterization Studies required that the U.S. Department of Energy develop a Reclamation Standards and Monitoring Plan to evaluate the success of reclamation efforts. According to the Reclamation Standards and Monitoring Plan, reclaimed sites will be monitored periodically, remediated if necessary, and eventually compared to an appropriate reference area to determine whether reclamation goals have been achieved and the site can be released from further monitoring. Plant cover, density, and species richness (success parameters) on reclaimed sites are compared to 60 percent of the values (success criteria) for the same parameters on the reference area. Small sites (less than 0.1 ha) are evaluated for release using qualitative methods while large sites (greater than 0.1 ha) are evaluated using quantitative methods. In the summer of 2000, 31 small sites reclaimed in 1993 and 1994 were evaluated for reclamation success and potential release from further monitoring. Plant density, cover, and species richness were estimated on the C-Well Pipeline, UE-25 Large Rocks test site, and 29 ground surface facility test pits. Evidence of erosion, reproduction and natural recruitment, exotic species abundance, and animal use (key attributes) also were recorded for each site and used in success evaluations. The C-Well Pipeline and ground surface facility test pits were located in a ''Larrea tridentata - Ephedra nevadensis'' vegetation association while the UE-25 Large Rocks test site was located in an area dominated by ''Coleogyne ramosissima and Ephedra nevadensis''. Reference areas in the same vegetation associations with similar slope and aspect were chosen for comparison to

Site Release Reports for C-Well Pipeline, UE-25 Large Rocks Test Site, and 29 GSF Test Pits

Energy Technology Data Exchange (ETDEWEB)

K.E. Rasmuson

2002-04-02

The U.S. Department of Energy has implemented a program to reclaim lands disturbed by site characterization at Yucca Mountain. Long term goals of the program are to re-establish processes on disturbed sites that will lead to self-sustaining plant communities. The Biological Opinion for Yucca Mountain Site Characterization Studies required that the U.S. Department of Energy develop a Reclamation Standards and Monitoring Plan to evaluate the success of reclamation efforts. According to the Reclamation Standards and Monitoring Plan, reclaimed sites will be monitored periodically, remediated if necessary, and eventually compared to an appropriate reference area to determine whether reclamation goals have been achieved and the site can be released from further monitoring. Plant cover, density, and species richness (success parameters) on reclaimed sites are compared to 60 percent of the values (success criteria) for the same parameters on the reference area. Small sites (less than 0.1 ha) are evaluated for release using qualitative methods while large sites (greater than 0.1 ha) are evaluated using quantitative methods. In the summer of 2000, 31 small sites reclaimed in 1993 and 1994 were evaluated for reclamation success and potential release from further monitoring. Plant density, cover, and species richness were estimated on the C-Well Pipeline, UE-25 Large Rocks test site, and 29 ground surface facility test pits. Evidence of erosion, reproduction and natural recruitment, exotic species abundance, and animal use (key attributes) also were recorded for each site and used in success evaluations. The C-Well Pipeline and ground surface facility test pits were located in a ''Larrea tridentata - Ephedra nevadensis'' vegetation association while the UE-25 Large Rocks test site was located in an area dominated by ''Coleogyne ramosissima and Ephedra nevadensis''. Reference areas in the same vegetation associations with similar slope

Geological, geophysical investigations and seismotectonic analysis with reference to selection of site for nuclear power plants: a review

International Nuclear Information System (INIS)

Chaki, Anjan

2014-01-01

Geological, geophysical investigations and seismotectonic analysis play a major role in qualifying a proposed site for establishment of nuclear power plants. In an area, it is important to understand the aspects such as regional and local geology, geomorphology, tectonic settings, presence of active faults/capable faults, earthquake history and earthquake proneness, neotectonic activity, slope instability, subsidence, liquefaction, seismically induced flooding, tsunami and geohydrological conditions. Geological investigations comprise use of remote sensing and ground validation followed by geological mapping, identification of faults, near surface geological studies for foundation conditions, stratigraphic drilling, palaeoseismology, studies on engineering properties of rock and soil. Geophysical investigations provide insight into subsurface geology including concealed faults, elastic constants and hydrological conditions. Radon emanometry is a valuable tool in the initial stage to decipher subsurface active weak zones/fault lines. Seismotectonic analysis identifies the provinces of tectonic significance and their earthquake potential, thereby designating lineaments of consequence leading to their evaluation. This, in turn, determines the design basis earthquake parameter for the estimation of vibratory ground motion. This article provides certain measures to evaluate the suitability of the sites for the establishment of nuclear power plants in terms of geological, geophysical investigations and seismotectonic status. Atomic Minerals Directorate for Exploration and Research (AMD) had carried out seismotectonic analysis of the area around Kaiga, Narora, Kalpakkam, Kakrapar, Tarapur, Kudankulam and Rawatbhata Nuclear Power Projects, which were either in operation or under expansion and construction. Such analysis was extended to a number of proposed sites for establishing nuclear power plants in West Bengal, Bihar, Orissa, Andhra Pradesh, Gujrat, Madhya Pradesh

Site layout and balance of plant design for an accelerator-driven materials processing complex

Energy Technology Data Exchange (ETDEWEB)

Cunliffe, J.; Taussig, R.; Ghose, S. [Bechtel Corporation, San Francisco, CA (United States)] [and others

1995-10-01

High energy proton beam accelerators are under consideration for use in radioisotope production, surplus weapons material destruction, radioactive waste transmutation, and thorium-based energy conversion cycles. While there are unique aspects to each of these applications that must be accommodated in the design of the associated facility, all share a set of fundamental characteristics that in large measure dictate the site layout features and many balance-of-plant (BOP) design requirements found to be common to all. This paper defines these key design determinants and goes on to discuss the manner in which they have been accommodated in the pre-conceptual design for a particular materials production application. An estimate of the costs associated with this BOP design is also presented with the aim of guiding future evaluations where the basic plant designs are similar to that of this specific case.

Siting of nuclear desalination plants in Saudi Arabia: A seismic study

International Nuclear Information System (INIS)

Aljohani, M.S.; Abdul-Fattah, A.F.; Almarshad, A.I.

2005-01-01

This paper presents the selection criteria generally and seismic criteria specifically to select a suitable site in Saudi Arabia for a nuclear desalination plant. These criteria include geological, meteorological, cooling water supply discharge, transport infrastructure, population, electric grid, water network capacity, environmental impact and airport movement. The seismicity of the Arabian peninsula for the locations of seismic activity along the Red Sea and the Arabian Gulf coastlines from 1973 to 2000 was studied carefully. This study included towns and locations along the east and west coastlines and their distances from the seismic event site. The results showed that Rabigh City along the west coast of Saudi Arabia is a good site to build a nuclear desalination plant. This is because of the following reasons: good seismic stability; good weather statistics; no flooding; mild wave conditions; good supply and discharge; good transportation infrastructure; low population area; very close to the huge electric grid. (author)

Demographic survey around proposed nuclear power plant site in Haryana covering 30 km radius area from the site

International Nuclear Information System (INIS)

Garg, V.K.

2013-01-01

This study was planned to have a demographic survey of the households living within 30 km radius of the proposed site. Objectives of the present study were to attain the quantitative baseline demographic data around (within 30 km radius) the proposed site of nuclear power plant, zone-wise and sector-wise distribution of the population around proposed site up to a distance of 30 km from the site, to obtain the data on socio-economic, cultural, and religious perspectives of the target populations, to obtain the data on disease/illness pattern in the target population, health status and mortality rate

Pinellas Plant annual site environmental report for calendar year 1995

International Nuclear Information System (INIS)

1996-05-01

Lockheed Martin Specialty Components, Inc., and the US Department of Energy are committed to successfully administering a high-quality Environmental, Safety and Health Program at the Pinellas Plant in Pinellas County, Florida. Part of this commitment includes accurately documenting and communicating to the Pinellas Plant stakeholders the results of the Pinellas Plant's environmental compliance and monitoring activities. The Annual Site Environmental Report presents a comprehensive summary of the results of the Environmental Monitoring, Waste Management, and Environmental Restoration Programs at the Pinellas Plant for 1995. This report also includes the plant's performance in the areas of compliance with applicable regulatory requirements and standards and identifies major Environmental, Safety and Health Program initiatives and accomplishments for 1995. As a result of the end of the Department of Energy's Defense Programs mission (weapons production) on September 30, 1994, considerable changes at the Pinellas Plant are occurring. The Department of Energy's Environmental Management is now the landlord of the Pinellas Plant to facilitate the plant's new mission of transition to alternate use in support of economic development and safe shutdown. The Department of Energy sold the Pinellas Plant to the Pinellas County Industry Council in March 1995, and it is leasing back a portion of the plant through September 1997, to complete the safe shutdown and transition activities

The opportunities and challenges of multi-site evaluations: lessons from the jail diversion and trauma recovery national cross-site evaluation.

Science.gov (United States)

Stainbrook, Kristin; Penney, Darby; Elwyn, Laura

2015-06-01

Multi-site evaluations, particularly of federally funded service programs, pose a special set of challenges for program evaluation. Not only are there contextual differences related to project location, there are often relatively few programmatic requirements, which results in variations in program models, target populations and services. The Jail Diversion and Trauma Recovery-Priority to Veterans (JDTR) National Cross-Site Evaluation was tasked with conducting a multi-site evaluation of thirteen grantee programs that varied along multiple domains. This article describes the use of a mixed methods evaluation design to understand the jail diversion programs and client outcomes for veterans with trauma, mental health and/or substance use problems. We discuss the challenges encountered in evaluating diverse programs, the benefits of the evaluation in the face of these challenges, and offer lessons learned for other evaluators undertaking this type of evaluation. Copyright © 2015 Elsevier Ltd. All rights reserved.

Re-assessment of plant carbon dynamics at the Duke free-air CO2 enrichment site: interactions of atmospheric [CO2] with nitrogen and water availability over stand development

Science.gov (United States)

Heather R. McCarthy; Ram Oren; Kurt H Johnsen; Anne Gallet-Budynek; Seth G. Pritchard; Charles W Cook; Shannon L. LaDeau; Robert B. Jackson; Adrien C. Finzi

2010-01-01

The potential for elevated [CO2]-induced changes to plant carbon (C) storage, through modifications in plant production and allocation of C among plant pools, is an important source of uncertainty when predicting future forest function. Utilizing 10 yr of data from the Duke free-air CO2 enrichment site, we evaluated the...

Brazilian nuclear power plants decommissioning plan for a multiple reactor site

Energy Technology Data Exchange (ETDEWEB)

Monteiro, Deiglys B.; Moreira, Joao M.L.; Maiorino, Jose R., E-mail: deiglys.monteiro@ufabc.edu.br, E-mail: joao.moreira@ufabc.edu.br, E-mail: joserubens.maiorino@ufabc.edu.br [Universidade Federal do ABC (CECS/UFABC), Santo Andre, SP (Brazil). Centro de Engenharia, Modelagem e Ciencias Aplicadas. Programa de Pos-Graduacao em Energia e Engenharia da Energia

2015-07-01

Actually, Brazil has two operating Nuclear Power Plants and a third one under construction, all at Central Nuclear Almirante Alvaro Alberto - CNAAA. To comply with regulatory aspects the power plants operator, Eletronuclear, must present to Brazilian Nuclear Regulatory Agency, CNEN, a decommissioning plan. Brazilian experience with decommissioning is limited because none of any nuclear reactor at the country was decommissioned. In literature, decommissioning process is well described despite few nuclear power reactors have been decommissioned around the world. Some different approach is desirable for multiple reactors sites, case of CNAAA site. During the decommissioning, a great amount of wastes will be produced and have to be properly managed. Particularly, the construction of Auxiliary Services on the site could be a good choice due to the possibility of reducing costs. The present work intends to present to the Eletronuclear some aspects of the decommissioning concept and decommissioning management, storage and disposal de wastes, based on the available literature, regulatory standards of CNEN and international experience as well as to suggest some solutions to be implemented at CNAAA site before starts the decommissioning project in order to maximize the benefits. (author)

Brazilian nuclear power plants decommissioning plan for a multiple reactor site

International Nuclear Information System (INIS)

Monteiro, Deiglys B.; Moreira, Joao M.L.; Maiorino, Jose R.

2015-01-01

Actually, Brazil has two operating Nuclear Power Plants and a third one under construction, all at Central Nuclear Almirante Alvaro Alberto - CNAAA. To comply with regulatory aspects the power plants operator, Eletronuclear, must present to Brazilian Nuclear Regulatory Agency, CNEN, a decommissioning plan. Brazilian experience with decommissioning is limited because none of any nuclear reactor at the country was decommissioned. In literature, decommissioning process is well described despite few nuclear power reactors have been decommissioned around the world. Some different approach is desirable for multiple reactors sites, case of CNAAA site. During the decommissioning, a great amount of wastes will be produced and have to be properly managed. Particularly, the construction of Auxiliary Services on the site could be a good choice due to the possibility of reducing costs. The present work intends to present to the Eletronuclear some aspects of the decommissioning concept and decommissioning management, storage and disposal de wastes, based on the available literature, regulatory standards of CNEN and international experience as well as to suggest some solutions to be implemented at CNAAA site before starts the decommissioning project in order to maximize the benefits. (author)

Waste Isolation Pilot Plant site environmental report for calendar year 1990

International Nuclear Information System (INIS)

1990-01-01

The US Department of Energy (DOE) Waste Isolation Pilot Plant (WIPP) Operational Environmental Monitoring Plan (OEMP) monitors a comprehensive set of parameters in order to detect any potential environmental impacts and establish baselines for future quantitative environmental impact evaluations. Surface water and groundwater, soil, and biotics are measured for background radiation. Nonradiological environmental monitoring activities include meteorological, air quality, soil properties, and the status of the local biological community. Ecological studies focus on the immediate area surrounding the site with emphasis on the salt storage pile, whereas baseline radiological surveillance covers a broader geographic area including nearby ranches, villages, and cities. Since the WIPP is still in a preoperational state, no waste has been received; therefore, certain elements required by Order DOE 5400.1 are not presented in this report. 15 figs. 19 tabs

Waste Isolation Pilot Plant site environmental report for calendar year 1990

Energy Technology Data Exchange (ETDEWEB)

1990-01-01

The US Department of Energy (DOE) Waste Isolation Pilot Plant (WIPP) Operational Environmental Monitoring Plan (OEMP) monitors a comprehensive set of parameters in order to detect any potential environmental impacts and establish baselines for future quantitative environmental impact evaluations. Surface water and groundwater, soil, and biotics are measured for background radiation. Nonradiological environmental monitoring activities include meteorological, air quality, soil properties, and the status of the local biological community. Ecological studies focus on the immediate area surrounding the site with emphasis on the salt storage pile, whereas baseline radiological surveillance covers a broader geographic area including nearby ranches, villages, and cities. Since the WIPP is still in a preoperational state, no waste has been received; therefore, certain elements required by Order DOE 5400.1 are not presented in this report. 15 figs. 19 tabs.

CHEMISTRY OF PLANTS AND RECLAIMED GROUNDS ON SODA WASTE SITE AT JANIKOWO

Directory of Open Access Journals (Sweden)

Jan Siuta

2014-10-01

Full Text Available The paper presents the state of soda waste dumping site prior to reclamation, including the initial vegetation and properties of local grounds, the chemistry of plants colonizing the alkaline grounds in 2013 as well as the comparison of mineral element contents in leaves of trees spontaneously growing on the soda waste site in the years 2000 and 2013. The paper consists an integral part of a wider work concerning the effectiveness of sewage sludge application for bioremediation of highly saline and alkaline waste at the Janikowo Soda Plant. The spontaneous vegetation on soda waste in 2000 was scarce and patchy, its development conditioned by local microrelief where depressions provided water for plant establishment. The main species entering the site included grasses (Lolium perenne, Calamagrostis epigeios and herbs (Reseda lutea, Tussilago farfara and Picris hieracioides. The physico-chemical properties of waste grounds varied widely both horizontally and spatially. In 2013, the reclaimed dumping site was covered by a well-established meadow-likevegetation and the soil top layer (0–5 cm contained 9.2–13.9% Ca and 15–161 mg Cl/kg, at pH 7.6–7.8. The underlying 10–20 cm layer contained 21.1–63.3% Ca and 204–3110 mg Cl/kg, at pH 7.93–9.04. In the deeper 40-60 cm layer there was found 30.0-37.5% Ca and 9 920-16 320 mg Cl/kg, at pH 11.5–12.1. The vegetation growing in the vicinity of soil profiles contained: 1.65–3.36% N; 0.25–0.43% P; 1.38–2.95% K; 0.33–1.10 % Ca and 0.13–0.54% Mg. The contents of heavy metals in plants approximated the average amounts found in meadow clippings in Poland. The contents of main nutrients in leaves of trees spontaneously growing on the waste site were significantly higher in 2013 (2.70–3.21% N; 0.25–0.34% P and 0.98–1.75% K than in the year 2000 (1.70–2.04% N; 0.11–0.21% P and 0.54–0.80% K. The application of sewage sludge and subsequent fertilization of vegetation on waste

Air toxics evaluation for a nuclear power plant

International Nuclear Information System (INIS)

Lokey, D.; Orr, W.

1994-01-01

An emission inventory of nonradiological hazardous air pollutants (HAP) was prepared for TVA's Browns Ferry Nuclear Plant (BFN). The purpose of this effort was to determine whether BFN is a major HAP emission source. About 40 specific HAP were identified in products used at FBN. HAP emission totals from BFN were estimated at 6 T/Y, well below the major-source cutoff. Off-site waste disposal reduced gross emission estimates by about 8 percent. HAP emission evaluation by product categories showed the largest portion due to paints and coatings, followed by cleaning compounds. HAP emission breakdown by chemical species showed xylene to be the predominate HAP emitted, followed by methyl ethyl ketone

Identification and screening of hazards for the external event PRA - External hazard identification, screening and studies for a new plant site

International Nuclear Information System (INIS)

Hellander, Juho

2014-01-01

Fennovoima is constructing a new nuclear power plant on a greenfield site in Northern Finland. Various evaluations for site-specific hazards are needed to ensure sufficient plant design basis values, proper design solutions and to provide input for the PRA model. This paper presents the general process used in identifying the relevant site-specific external hazards. The applicable legislative requirements, guides and standards regarding external hazards and external event PRA shall be identified. Based on these, an initial comprehensive list of events should be compiled. The initial list shall be filtered to exclude irrelevant events. Events can be screened out if the probability is very low or if the consequences are only mild. Events with similar consequences should be combined. Events can be grouped in several ways, and in this paper the risks are categorized into events related to air, water bodies, ground and human behaviour. In addition, the simultaneously occurring combinations of events should be identified. The paper also summarizes some hazard studies already performed and required in the future in Fennovoima's project. A comprehensive study is ongoing related to earthquake risks. The study aims at identifying all relevant seismic sources and taking into account various expert opinions in seismic modelling. Also frazil ice and anchor ice studies are being performed to eliminate the risk of cooling water intake blockage due to ice. In addition, some other study areas are mentioned. This paper presented a list of Finnish and international guides and standards useful in evaluating external hazards. Also a methodology was presented to identify and screen site-specific hazards in a new nuclear power plant project. The screened list of relevant events for the Hanhikivi site requiring further studies was presented. Also the studies needed in different phases of a new nuclear power plant project were discussed. Some specific studies regarding earthquakes and

The Role of Tectonic and Seismicity in Siting of Nuclear Power Plant

International Nuclear Information System (INIS)

Abdel Aziz, M.A.H.

2008-01-01

The site selection for the a nuclear power plant (NPP) is controlled by many criteria. One of the most important criterion is the tectonic and seismicity of the site and its surroundings. Since, it is preferable the site in concern is characterized by low tectonic and low seismicity to avoid the damage effects associated with the occurrence of destructive earthquakes. The investigation of the tectonic and seismicity maps of egypt has been carried out to candidate potential areas or sites for nuclear power plant installation from seismicity point of view. Also, the design basis ground motion in terms of peak ground acceleration and response spectra of some of the potential sites are defined through the conduct of probabilistic seismic hazard analysis The study revealed that although there is no criterion to exclude areas of high tectonic and high seismicity as potential sites for nuclear power plant installation but, it is preferable avoiding such areas. This is attributed to the critical seismic curve that characterizes such areas and is required high seismic design levels to resist the destructive vibratory ground motion associated with the expected earthquake. Consequently, the required high seismic design levels will have a negative impact on the economic cost of the facility compared with that built in low and moderate seismic areas. Hence, areas like the gulf of suez, the northern part of the Red Sea and the southern part of Sinai Peninsula should be avoided as potential sites for NPP from the tectonic and seismicity point of view. On the other hand, areas like Nile delta and its valley, the Northern and Southern parts of Western desert and the central and southern parts of the Eastern Desert should be candidate as potential sites on condition, the other criteria meet the IAEA's regulations. Also, the seismic hazard curve of the Northwest littoral zone reflects low design basis ground motion values compared with the Nile delta region

Losses of off-site power at U.S. nuclear power plants -- through 1995. Final report

International Nuclear Information System (INIS)

Wyckoff, H.

1996-04-01

This report provides a database and summary analysis of losses of off-site power at US nuclear generating units. It includes the 16 years 1980 through 1995. This is the twelfth update of this database and analysis. During 1994 there were no losses of all off-site power and in 1995 only two short losses. Both the short term and long term US loss of all off-site power experience is extremely favorable. The frequency of losing all off-site power is an important input to many nuclear plant safety assessments. The industry's loss of all off-site power experience that is set forth in this report can provide perspective to plant specific probabilistic safety assessments

Maryland Power Plant Siting Project: an application of the ORNL-Land Use Screening Procedure

International Nuclear Information System (INIS)

Dobson, J.E.

1975-01-01

Since 1974 the Resource Analysis Group in the Regional and Urban Studies Section of the Oak Ridge National Laboratory (ORNL) has been engaged in developing a procedure for regional and local siting analysis known as the ORNL Land Use Screening Procedure (LUSP). This document is the final report of the Maryland Power Plant Siting Project (MPPSP) in which the ORNL LUSP was used to identify candidate areas for power plant sites in northern Maryland. Numerous candidate areas are identified on the basis of four different siting objectives: the minimization of adverse ecologic impact, the minimization of adverse socioeconomic impact, the minimization of construction and operating costs, and a composite of all siting objectives. Siting criteria have been defined for each of these objectives through group processing techniques administered to four different groups of siting specialists. The siting priorities and opinions of each group have been expressed quantitatively and applied to a geographic information system containing 52 variables for each 91.8-acre cell in the northern eight counties of Maryland

Maryland Power Plant Siting Project: an application of the ORNL-Land Use Screening Procedure

Energy Technology Data Exchange (ETDEWEB)

Dobson, J.E.

1975-01-01

Since 1974 the Resource Analysis Group in the Regional and Urban Studies Section of the Oak Ridge National Laboratory (ORNL) has been engaged in developing a procedure for regional and local siting analysis known as the ORNL Land Use Screening Procedure (LUSP). This document is the final report of the Maryland Power Plant Siting Project (MPPSP) in which the ORNL LUSP was used to identify candidate areas for power plant sites in northern Maryland. Numerous candidate areas are identified on the basis of four different siting objectives: the minimization of adverse ecologic impact, the minimization of adverse socioeconomic impact, the minimization of construction and operating costs, and a composite of all siting objectives. Siting criteria have been defined for each of these objectives through group processing techniques administered to four different groups of siting specialists. The siting priorities and opinions of each group have been expressed quantitatively and applied to a geographic information system containing 52 variables for each 91.8-acre cell in the northern eight counties of Maryland.

Evaluation of a committed fusion site. Final report

International Nuclear Information System (INIS)

1979-07-01

This report is divided into five technical sections. Section 2 is a summary. In Section 3, which covers device and site analyses the major characteristics of devices that might be placed at the site, as envisioned by major fusion laboratories, are described; the characteristics of a site (baseline site) which would accommodate these devices are defined; and various approaches to a committed site meeting the baseline site requirements are discussed. Section 4 describes the scenarios selected to represent possible site development outcomes; these scenarios are evaluated with respect to comparative cost and schedule effects. Section 5 presents a brief evaluation of the effects fusion-fission hybrids might have on the committed site. Major conclusions and recommendations are discussed in Section 6

Effects of Mechanical Site Preparation on Growth of Oaks Planted on Former Agricultural Fields

Directory of Open Access Journals (Sweden)

John D. Hodges

2011-12-01

Full Text Available Mechanical site preparation is frequently proposed to alleviate problematic soil conditions when afforesting retired agricultural fields. Without management of soil problems, any seedlings planted in these areas may exhibit poor growth and survival. While mechanical site preparation methods currently employed in hardwood afforestation are proven, there is a substantial void in research comparing subsoiling, bedding, and combination plowing treatments. A total of 4,320 bare-root Nuttall oak (Quercus texana Buckley, Shumard oak (Quercus shumardii Buckley, and swamp chestnut oak (Quercus michauxii Nutt. seedlings were planted in February 2008 on three Mississippi sites. All sites were of comparable soils and received above average precipitation throughout the three-year duration of the study. Four site preparation treatments were replicated at each site, with 480 seedlings planted in each of nine replications, and a total of 1,440 seedlings per species planted across all sites. Mechanical treatments were installed using 3.1 m row centers, with treatments as follows: control, subsoiling, bedding, and combination plowing. Treatment effects on seedling height, groundline diameter (GLD, and survival were analyzed. Seedlings exhibited greater height in bedded and combination plowed areas (79.7 cm to 102.7 cm and 82.6 cm to 100.1 cm, respectively compared to subsoiled or control areas (70.4 cm to 84.6 cm and 71.4 cm to 86.9 cm, respectively. Greater GLD was observed in bedded and combination plowed areas (11.9 mm to 18.4 mm and 12.2 mm to 18.3 mm, respectively compared to subsoiled or control areas (10.2 mm to 14.6 mm and 10.5 mm to 15.6 mm, respectively. Survival was high for this study (94.%, and no differences were detected among treatments.

Should the public be encouraged to visit nuclear plant sites?

International Nuclear Information System (INIS)

Ferte, J. de la

1993-01-01

As we all know, technological progress does not only depend on the innovation capacity of scientists and engineers or the sophistication of technology, but also on public acceptance. People - today - are not only more curious about new applications of technology but also more inquiring about their potential impact on their own safety and environment. This is particularly true in the nuclear field, where the people are afraid of nuclear installations and processes unknown to them. On the contrary, the more opportunities they have to see or live near nuclear plants, the less they are inclined to reject them as a whole. The past two decades have confirmed the increasing importance of visitor centres at nuclear plant sites as a major communication tool between the nuclear industry and the public. Already today, for example, 16% of the US public and 11% of the French public have visited a nuclear power plant or its information centre. A rich experience is therefore available from existing visitor centres at nuclear power stations in most industrialised countries. Furthermore, the construction and industrial operation of new facilities in the nuclear fuel cycle presents new challenges in terms of public understanding and acceptance which are progressively taken into account. As a result, visitor centres with new communication strategies and tools are now being put in place at radioactive waste management sites and nuclear fuel cycle sites as well as near nuclear installations being dismantled. The OECD Nuclear Energy Agency (NEA) organised an international Seminar in November 1992 in Madrid (Spain) in co-operation with the Spanish Agency for the Management of Radioactive Waste (ENRESA) and the Union of Spanish Electricity Utilities (UNESA) to: 1. take stock of the experience of OECD countries in the design and operation of visitor centres; 2. assess the educational and information methods and tools used in these centres, and 3. measure their impact on public opinion and

Should the public be encouraged to visit nuclear plant sites?

Energy Technology Data Exchange (ETDEWEB)

Ferte, J de la [External Relations and Public Affairs, OECD Nuclear Energy Agency, Paris (France)

1993-07-01

As we all know, technological progress does not only depend on the innovation capacity of scientists and engineers or the sophistication of technology, but also on public acceptance. People - today - are not only more curious about new applications of technology but also more inquiring about their potential impact on their own safety and environment. This is particularly true in the nuclear field, where the people are afraid of nuclear installations and processes unknown to them. On the contrary, the more opportunities they have to see or live near nuclear plants, the less they are inclined to reject them as a whole. The past two decades have confirmed the increasing importance of visitor centres at nuclear plant sites as a major communication tool between the nuclear industry and the public. Already today, for example, 16% of the US public and 11% of the French public have visited a nuclear power plant or its information centre. A rich experience is therefore available from existing visitor centres at nuclear power stations in most industrialised countries. Furthermore, the construction and industrial operation of new facilities in the nuclear fuel cycle presents new challenges in terms of public understanding and acceptance which are progressively taken into account. As a result, visitor centres with new communication strategies and tools are now being put in place at radioactive waste management sites and nuclear fuel cycle sites as well as near nuclear installations being dismantled. The OECD Nuclear Energy Agency (NEA) organised an international Seminar in November 1992 in Madrid (Spain) in co-operation with the Spanish Agency for the Management of Radioactive Waste (ENRESA) and the Union of Spanish Electricity Utilities (UNESA) to: 1. take stock of the experience of OECD countries in the design and operation of visitor centres; 2. assess the educational and information methods and tools used in these centres, and 3. measure their impact on public opinion and

Tornado damage at the Grand Gulf, Mississippi nuclear power plant site: aerial and ground surveys

International Nuclear Information System (INIS)

Fujita, T.T.; McDonald, J.R.

1978-05-01

A tornado struck the Grand Gulf nuclear power generating station, Port Gibson, Mississippi, about 11:30 p.m. on April 17, 1978. Storm damage investigators from the University of Chicago and Texas Tech University were dispatched to survey the damage. The meteorological situation that spawned the Grand Gulf tornado and seven others in the area is discussed. Aerial surveys of the entire damage path and detailed surveys of the plant site are presented. An engineering evaluation of the damage is also presented based primarily on information gained from detailed ground surveys

Vascular plants of the Nevada Test Site and Central-Southern Nevada: ecologic and geographic distributions

Energy Technology Data Exchange (ETDEWEB)

Beatley, J.C.

1976-01-01

The physical environment of the Nevada Test Site and surrounding area is described with regard to physiography, geology, soils, and climate. A discussion of plant associations is given for the Mojave Desert, Transition Desert, and Great Basin Desert. The vegetation of disturbed sites is discussed with regard to introduced species as well as endangered and threatened species. Collections of vascular plants were made during 1959 to 1975. The plants, belonging to 1093 taxa and 98 families are listed together with information concerning ecologic and geographic distributions. Indexes to families, genera, and species are included. (HLW)

Public regulation of site selection for nuclear power plants. Present procedures and reform proposals: an annotated bibliography

International Nuclear Information System (INIS)

Klema, E.D.; West, R.L.

1977-01-01

Part I of this bibliography contains literature which describes the process of power-plant siting as conducted by the utilities, siting procedures at the point of initiative, analytical tools employed or proposed for site assessment by enterprises in the industry, and the wide range of considerations which the utilities take into account in making site assessments. Part II contains studies and reports on the structure and process of public regulation of power plant siting: the licensing of nuclear facilities by the NRC under terms of the special Government powers in the field of nuclear energy that have evolved since World War II; the steady expansion of regulatory objectives bearing on site approval for nuclear power plants; local government, State, and other Federal agency regulation of siting; survey siting procedures in other countries; the role of regulatory delay in the long lead-time required for construction and operation of nuclear plants. Part III incudes citations on regulatory structure and practice that are unresponsive to the public interest; regulatory decision making's insufficient accessible to public scrutiny and participation; and regulatory procedures that encourage and protect inefficient practices of the regulated industries. Some legal decisions and case studies are included. Part IV, Reform Proposals, includes citations on regulatory reform and reform of siting regulations. Abstracts are provided with 157 of the citations with many more papers cited by title, author, and accession data

Fruiting of browse plants affected by pine site preparation in east Texas

Science.gov (United States)

John J. Stransky; Douglas Richardson

1977-01-01

Pine planting sites prepared by burning yielded 120 kg/ha of browse fruits the third growing season after site treatment. Control plots yielded 74, KG-bladed plots 57, and chopped plots 41 kg/ha. Blackberries, American beautyberry, sumac, Sebastian bush, muscadine grape, blueberries, and southern wax-myrtle were the principal species. Most fruit was available in summer...

Archaeological reconnaissance of a proposed site for the Waste Isolation Plant (WIPP)

International Nuclear Information System (INIS)

Nielsen, J.

1976-01-01

An archaeological reconnaissance was carried out on Sections 20, 21, 28, and 29 of T 22 S, R 31 E, Eddy County, NM, the core area of a site proposed for disposal of radioactive waste in bedded salt (the Waste Isolation Pilot Plant). This site is located in the Los Medanos area east of Carlsbad, NM. Results of the survey are presented in sections on survey techniques, geology, terrain, floristics, cultural resources, theoretical considerations, site description, and recommendations

Cytotoxicity evaluation of sixteen Nigerian medicinal plant extracts ...

African Journals Online (AJOL)

As part of our evaluation of plants from the Nigerian ethnobotany,sixteen extracts from fourteen medicinal plants were evaluated for toxicity and inhibition of tumour cell growth using human rhabdomyosarcoma(RD) cell line. The plant samples were extracted by maceration in methanol at room temperature and were ...

A new methodology for repository site suitability evaluation

International Nuclear Information System (INIS)

Miller, I.; Kossik, R.; Cunnane, M.

1992-01-01

Golder Associates Inc. (GAI) has developed a probabilistic total system performance assessment and strategy evaluation model (RIP) which can be applied in an iterative manner to evaluate repository site suitability and guide site characterization. The major portion of the software is the performance assessment model, which consists of a series of coupled component models for radionuclide transfer. The performance model itself is embedded within a decision analysis model which allows the user to evaluate alternative site characterization strategies. This paper provides an overview of the methodology, and summarizes the basic concepts of RIP

The link between off-site-emergency planning and plant-internal accident management

Energy Technology Data Exchange (ETDEWEB)

Braun, H.; Goertz, R.

1995-02-01

A variety of accident management measures has been developed and implemented in the German nuclear power plants. They constitute a fourth level of safety in the defence-in-depth concept. The containment venting system is an important example. A functioning link with well defined lines of communication between plant-internal accident management and off-site disaster emergency planning has been established.

Preliminary evaluation of licensing issues associated with U.S.-sited CANDU-PHW nuclear power plants

International Nuclear Information System (INIS)

van Erp, J.B.

1977-12-01

The principal safety-related characteristics of current CANDU-PHW power plants are described, and a distinction between those characteristics which are intrinsic to the CANDU-PHW system and those that are not is presented. An outline is given of the main features of the Canadian safety and licensing approach. Differences between the U.S. and Canadian approach to safety and licensing are discussed. Some of the main results of the safety analyses, routinely performed for CANDU-PHW reactors, are presented. U.S.-NRC General Design Criteria are evaluated as regards their applicability to CANDU-PHW reactors; vice-versa the CANDU-PHW reactor is evaluated with respect to its conformance to the U.S.-NRC General Design Criteria. A number of design modifications are proposed to be incorporated into the CANDU-PHW reactor in order to facilitate its introduction into the U.S

Preliminary evaluation of licensing issues associated with U. S. -sited CANDU-PHW nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

van Erp, J B

1977-12-01

The principal safety-related characteristics of current CANDU-PHW power plants are described, and a distinction between those characteristics which are intrinsic to the CANDU-PHW system and those that are not is presented. An outline is given of the main features of the Canadian safety and licensing approach. Differences between the U.S. and Canadian approach to safety and licensing are discussed. Some of the main results of the safety analyses, routinely performed for CANDU-PHW reactors, are presented. U.S.-NRC General Design Criteria are evaluated as regards their applicability to CANDU-PHW reactors; vice-versa the CANDU-PHW reactor is evaluated with respect to its conformance to the U.S.-NRC General Design Criteria. A number of design modifications are proposed to be incorporated into the CANDU-PHW reactor in order to facilitate its introduction into the U.S.

Waste Isolation Pilot Plant Annual Site Environmental Report for 2012

Energy Technology Data Exchange (ETDEWEB)

None

2013-09-01

The purpose of the Waste Isolation Pilot Plant (WIPP) Annual Site Environmental Report for 2012 (ASER) is to provide information required by U.S. Department of Energy (DOE) Order 231.1B, Environment, Safety, and Health Reporting. Specifically, the ASER presents summary environmental data to: Characterize site environmental management performance; Summarize environmental occurrences and responses reported during the calendar year; Confirm compliance with environmental standards and requirements; Highlight significant environmental accomplishments, including progress toward the DOE Environmental Sustainability Goals made through implementation of the WIPP Environmental Management System (EMS).

Building dismantlement and site remediation at the Apollo Fuel Plant: When is technology the answer?

International Nuclear Information System (INIS)

Walton, L.

1995-01-01

The Apollo fuel plant was located in Pennsylvania on a site known to have been used continuously for stell production from before the Civil War until after World War II. Then the site became a nuclear fuel chemical processing plants. Finally it was used to convert uranium hexafluoride to various oxide fuel forms. After the fuel manufacturing operations were teminated, the processing equipment was partially decontaminated, removed, packaged and shipped to a licensed low-level radioactive waste burial site. The work was completed in 1984. In 1990 a detailed site characterization was initiated to establishe the extent of contamination and to plan the building dismantlement and soil remediation efforts. This article discusses the site characterization and remedial action at the site in the following subsections: characterization; criticality control; mobile containment; soil washing; in-process measurements; and the final outcome of the project

Wind data for wind driven plant. [site selection for optimal performance

Science.gov (United States)

Stodhart, A. H.

1973-01-01

Simple, averaged wind velocity data provide information on energy availability, facilitate generator site selection and enable appropriate operating ranges to be established for windpowered plants. They also provide a basis for the prediction of extreme wind speeds.

Insights from Siting New Nuclear Power Plants in the Central and Eastern United States

International Nuclear Information System (INIS)

Munson, Clifford G.; Kugler, Andrew J.

2011-01-01

The staff of the U.S. Nuclear Regulatory Commission (NRC) has completed its review for four early site permits and for four standard reactor designs. It is currently reviewing applications for fourteen combined license applications and three additional reactor designs. The staff is applying lessons it has learned from the reviews to date to the review work going forward. The licensing process being used by current applicants differs significantly from that used by the current operating fleet. The previous process required two steps. First an applicant had to obtain a construction permit to build the plant. Then, near the end of construction, the applicant had to obtain an operating license. Under the process in Part 52, an applicant can apply for a combined license (COL) that allows construction and (once certain conditions are met) operation of a new plant - a one-step process. An applicant for a COL may reference an early site permit (ESP13), a standard design certification, both, or neither. In addition to developing Part 52, the NRC also revised CFR Part 100 by adding Subpart B, which includes sections 100.21, 'Non-seismic siting criteria', and 100.23, 'Geologic and seismic siting criteria'. The NRC staff also revised the Standard Review Plan (NUREG-0800) and developed Regulatory Guide (RG) 1.206, 'Combined License Applications for Nuclear Power Plants (LWR Edition).' The NRC staff incorporated into the revision of NUREG-0800 and development of RG 1.206 some early lessons learned from its review of the first three ESPs. Staff work begins before the application is received, as the staff interacts with the applicant to identify issues that will require special treatment or specific staff resources. After the application is submitted, if the NRC finds the application acceptable, the safety and environmental reviews begin, proceeding in parallel. The safety review culminates in the issuance of a safety evaluation report (SER) after it

Global positioning site environment evaluator

International Nuclear Information System (INIS)

Leffler, S.; Reeser, H.G.; Zaker, E.; Hansen, W.; Sikorski, R.W.

1990-01-01

Development of an innovative, integrated, automated system (Global Positioning Site Environment Evaluator - GPSEETM) for surveying contaminated waste sites is described. This system makes novel use of the Global Positioning System (GPS) satellite constellation for establishing specific locations and current times for surveying radioactive, hazardous, or mixed-waste sites. GPSEE may also be used for waste site contamination surveys after remediation activities to ensure environmental remediation is complete. A base station is established for collecting and recording data and directing field operations for field stations which may be located many miles from the base station. The field operators collect site surveying and contamination data utilizing a variety of chemical and radiological sensors. A major goal for the data collection process is to collect all data utilizing in situ sensors, thereby minimizing the need for collecting soil and water samples. Site contamination data is transmitted electronically to the base station for recording and processing. The GPSEE system is being developed for use at DOE/DOD and a variety of industrial facilities. 3 figs

Integrated Plant Safety Assessment, Systematic Evaluation Program, Palisades Plant (Docket No. 50-255)

International Nuclear Information System (INIS)

1983-11-01

This report documents the review completed under the SEP for those issues that required refined engineering evaluations or the continuation of ongoing evaluations after the Final IPSAR for the Palisades Plant was issued. The review has provided for (1) an assessment of the significance of differences between current technical positions on selected safety issues and those that existed when the Palisades Plant was licensed, (2) a basis for deciding on how these differences should be resolved in an integrated plant review, and (3) a documented evaluation of plant safety when the supplement to the Final IPSAR and the Safety Evaluation Report for converting the license from a provisional to a full-term license have been issued. The Final IPSAR and its supplement will form part of the bases for considering the conversion of the provisional operating license to a full-term operating license

Site descriptive modelling - strategy for integrated evaluation

International Nuclear Information System (INIS)

Andersson, Johan

2003-02-01

The current document establishes the strategy to be used for achieving sufficient integration between disciplines in producing Site Descriptive Models during the Site Investigation stage. The Site Descriptive Model should be a multidisciplinary interpretation of geology, rock mechanics, thermal properties, hydrogeology, hydrogeochemistry, transport properties and ecosystems using site investigation data from deep bore holes and from the surface as input. The modelling comprise the following iterative steps, evaluation of primary data, descriptive and quantitative modelling (in 3D), overall confidence evaluation. Data are first evaluated within each discipline and then the evaluations are checked between the disciplines. Three-dimensional modelling (i.e. estimating the distribution of parameter values in space and its uncertainty) is made in a sequence, where the geometrical framework is taken from the geological model and in turn used by the rock mechanics, thermal and hydrogeological modelling etc. The three-dimensional description should present the parameters with their spatial variability over a relevant and specified scale, with the uncertainty included in this description. Different alternative descriptions may be required. After the individual discipline modelling and uncertainty assessment a phase of overall confidence evaluation follows. Relevant parts of the different modelling teams assess the suggested uncertainties and evaluate the feedback. These discussions should assess overall confidence by, checking that all relevant data are used, checking that information in past model versions is considered, checking that the different kinds of uncertainty are addressed, checking if suggested alternatives make sense and if there is potential for additional alternatives, and by discussing, if appropriate, how additional measurements (i.e. more data) would affect confidence. The findings as well as the modelling results are to be documented in a Site Description

Gasbuggy Site Assessment and Risk Evaluation

Energy Technology Data Exchange (ETDEWEB)

None

2011-03-01

This report describes the geologic and hydrologic conditions and evaluates potential health risks to workers in the natural gas industry in the vicinity of the Gasbuggy, New Mexico, site, where the U.S. Atomic Energy Commission detonated an underground nuclear device in 1967. The 29-kiloton detonation took place 4,240 feet below ground surface and was designed to evaluate the use of a nuclear detonation to enhance natural gas production from the Pictured Cliffs Formation in the San Juan Basin, Rio Arriba County, New Mexico, on land administered by Carson National Forest. A site-specific conceptual model was developed based on current understanding of the hydrologic and geologic environment. This conceptual model was used for establishing plausible contaminant exposure scenarios, which were then evaluated for human health risk potential. The most mobile and, therefore, the most probable contaminant that could result in human exposure is tritium. Natural gas production wells were identified as having the greatest potential for bringing detonation-derived contaminants (tritium) to the ground surface in the form of tritiated produced water. Three exposure scenarios addressing potential contamination from gas wells were considered in the risk evaluation: a gas well worker during gas-well-drilling operations, a gas well worker performing routine maintenance, and a residential exposure. The residential exposure scenario was evaluated only for comparison; permanent residences on national forest lands at the Gasbuggy site are prohibited

Monitored retrievable storage facility site screening and evaluation report

International Nuclear Information System (INIS)

1985-05-01

The Nuclear Waste Policy Act of 1982 directs the Department of Energy to ''complete a detailed study of the need for and feasibility of, and to submit to the Congress a proposal for, the construction of one or more monitored retrievable storage facilities for high level radioactive waste and spent nuclear fuel.'' The Act directs that the proposal includes site specific designs. Further, the proposal is to include, ''for the first such facility, at least three alternative sites and at least five alternative combinations of such proposed site and facility designs...'' as well as a recommendation of ''the combination among the alternatives that the Secretary deems preferable.'' An MRS Site Screening Task Force has been formed to help identify and evaluated potential MRS facility sites within a preferred region and with the application of a siting process and criteria developed by the DOE. The activities of the task force presented in this report includes: site screening (Sections 3, 4, and 5), the MRS facilities which are to be sited are described; the criteria, process and outcome of the screening process is presented; and descriptions of the candidate MRS facility sites are given, and site evaluations (Sections 6 through 9) where the rational for the site evaluations are presented, along with each evaluation and findings of the Task Force

Monitored retrievable storage facility site screening and evaluation report

Energy Technology Data Exchange (ETDEWEB)

none,

1985-05-01

The Nuclear Waste Policy Act of 1982 directs the Department of Energy to complete a detailed study of the need for and feasibility of, and to submit to the Congress a proposal for, the construction of one or more monitored retrievable storage facilities for high level radioactive waste and spent nuclear fuel.'' The Act directs that the proposal includes site specific designs. Further, the proposal is to include, for the first such facility, at least three alternative sites and at least five alternative combinations of such proposed site and facility designs...'' as well as a recommendation of the combination among the alternatives that the Secretary deems preferable.'' An MRS Site Screening Task Force has been formed to help identify and evaluated potential MRS facility sites within a preferred region and with the application of a siting process and criteria developed by the DOE. The activities of the task force presented in this report includes: site screening (Sections 3, 4, and 5), the MRS facilities which are to be sited are described; the criteria, process and outcome of the screening process is presented; and descriptions of the candidate MRS facility sites are given, and site evaluations (Sections 6 through 9) where the rational for the site evaluations are presented, along with each evaluation and findings of the Task Force.

Plant species diversity as a driver of early succession in abandoned fields: a multi-site approach.

Science.gov (United States)

Van der Putten, W H; Mortimer, S R; Hedlund, K; Van Dijk, C; Brown, V K; Lepä, J; Rodriguez-Barrueco, C; Roy, J; Diaz Len, T A; Gormsen, D; Korthals, G W; Lavorel, S; Regina, I Santa; Smilauer, P

2000-07-01

Succession is one of the most studied processes in ecology and succession theory provides strong predictability. However, few attempts have been made to influence the course of succession thereby testing the hypothesis that passing through one stage is essential before entering the next one. At each stage of succession ecosystem processes may be affected by the diversity of species present, but there is little empirical evidence showing that plant species diversity may affect succession. On ex-arable land, a major constraint of vegetation succession is the dominance of perennial early-successional (arable weed) species. Our aim was to change the initial vegetation succession by the direct sowing of later-successional plant species. The hypothesis was tested that a diverse plant species mixture would be more successful in weed suppression than species-poor mixtures. In order to provide a robust test including a wide range of environmental conditions and plant species, experiments were carried out at five sites across Europe. At each site, an identical experiment was set up, albeit that the plant species composition of the sown mixtures differed from site to site. Results of the 2-year study showed that diverse plant species mixtures were more effective at reducing the number of natural colonisers (mainly weeds from the seed bank) than the average low-diversity treatment. However, the effect of the low-diversity treatment depended on the composition of the species mixture. Thus, the effect of enhanced species diversity strongly depended on the species composition of the low-diversity treatments used for comparison. The effects of high-diversity plant species mixtures on weed suppression differed between sites. Low-productivity sites gave the weakest response to the diversity treatments. These differences among sites did not change the general pattern. The present results have implications for understanding biological invasions. It has been hypothesised that alien

Economic evaluation of bids for nuclear power plants

International Nuclear Information System (INIS)

1976-01-01

The purpose of the guidebook is to assist an organisation responsible for a nuclear power project in evaluating and establishing an economic order of merit among competing bids. An approximate overall time schedule for a first nuclear power plant project is provided. A schematic outline of technical bid evaluation is given. The basic procedure of economic bid evaluation is outlined, e.g. evaluation of the present worth of all cost items of plant capital investment, of the nuclear cycle, of O and M costs (operation and maintenance costs), and of economic corrections. All these cost items are evaluated for the economic life of the plant and corrected for escalation where applicable

Land use suitability screening for power plant sites in Maryland

International Nuclear Information System (INIS)

Dobson, J.E.

1975-01-01

Since 1974 Oak Ridge National Laboratory (ORNL) has been engaged in developing an automated procedure for land use suitability screening. The Nuclear Regulatory Commission has funded the project to aid in the selection of power plant sites in Maryland. Its purpose is to identify candidate areas from which specific candidate sites can be chosen for detailed analyses. The ORNL approach assures that certain key variables are examined empirically for every cell in the study region before candidate sites are selected. Each variable is assigned an importance weight and compatibility score based upon its effect on the economic, social, or ecologic costs associated with construction in a given cell. The weighted scores for each variable are aggregated and output as a suitability score for each cell

On site selection of thermoelectric power plants in polluted environment

International Nuclear Information System (INIS)

Gheorghe, A.V.

1992-01-01

This paper discusses the environmental impact of combined heat-power plants. The selection of the site of these plants depends on the spatial distribution law of pollutants and their chemical interaction with environment. The solutions of a diffusion equation describing a system of chemically interacting pollutants are given and discussed. The environmental impacts are described in terms of wind and atmosphere stability, effective and built stack height and the source distance parameters. The optimal constructive solutions are judged upon the concentrations of sulfur and nitrogen oxides at the ground level which must be kept under the maximum admissible limit. (author). 8 figs

Monitored Retrievable Storage facility site screening and evaluation report

International Nuclear Information System (INIS)

1985-05-01

The Nuclear Waste Policy Act of 1982 directs the Department of Energy to ''complete a detailed study of the need for and feasibility of, and to submit to the Congress a proposal for, the construction of one or more monitored retrievable storage facilities for high level radioactive waste and spent nuclear fuel.'' The Act directs that the proposal includes site specific designs. Further, the proposal is to include, ''for the first such facility, at least three alternative sites and at least five alternative combinations of such proposed sites and facility designs hor-ellipsis'' as well as a recommendation of ''the combination among the alternatives that the Secretary deems preferable.'' An MRS Site Screening Task Force has been formed to help identify and evaluate potential MRS facility sites within a preferred region and with the application of a siting process and criteria developed by the DOE. The activities of the Task Force presented in this report, all site evaluations (sections 13 through 16) where the rationale for the site evaluations are presented, along with each evaluation and findings of the Task Force. This is Volume 3 of a three volume document. References are also included in this volume

Monitored retrievable storage facility site screening and evaluation report

International Nuclear Information System (INIS)

1985-05-01

The Nuclear Waste Policy Act of 1982 directs the Department of Energy to ''complete a detailed study of the need for and feasibility of, and to submit to the Congress a proposal for, the construction of one or more monitored retrievable storage facilities for high level radioactive waste and spent nuclear fuel.'' The Act directs that the proposal includes site specific designs. Further, the proposal is to include, ''for the first such facility, at least three alternative sites and at least five alternative combinations of such proposed sites and facility designs hor-ellipsis'' as well as a recommendation of ''the combination among the alternatives that the Secretary deems preferable.'' An MRS Site Screening Task Force has been formed to help identify and evaluate potential MRS facility sites within a preferred region and with the application of a siting process and criteria developed by the DOE. The activities of the Task Force presented in this report include: site evaluations (sections 10 through 12) where the rationale for the site evaluations are presented, along with each evaluation and findings of the Task Force. This in Volume 2 of a three volume document

Monitored retrievable storage facility site screening and evaluation report

Energy Technology Data Exchange (ETDEWEB)

none,

1985-05-01

The Nuclear Waste Policy Act of 1982 directs the Department of Energy to complete a detailed study of the need for and feasibility of, and to submit to the Congress a proposal for, the construction of one or more monitored retrievable storage facilities for high level radioactive waste and spent nuclear fuel.'' The Act directs that the proposal includes site specific designs. Further, the proposal is to include, for the first such facility, at least three alternative sites and at least five alternative combinations of such proposed sites and facility designs{hor ellipsis}'' as well as a recommendation of the combination among the alternatives that the Secretary deems preferable.'' An MRS Site Screening Task Force has been formed to help identify and evaluate potential MRS facility sites within a preferred region and with the application of a siting process and criteria developed by the DOE. The activities of the Task Force presented in this report include: site evaluations (sections 10 through 12) where the rationale for the site evaluations are presented, along with each evaluation and findings of the Task Force. This in Volume 2 of a three volume document.

Bird Pollinator Visitation is Equivalent in Island and Plantation Planting Designs in Tropical Forest Restoration Sites

Directory of Open Access Journals (Sweden)

Ginger M. Thurston

2013-03-01

Full Text Available Active restoration is one strategy to reverse tropical forest loss. Given the dynamic nature of climates, human populations, and other ecosystem components, the past practice of using historical reference sites as restoration targets is unlikely to result in self-sustaining ecosystems. Restoring sustainable ecological processes like pollination is a more feasible goal. We investigated how flower cover, planting design, and landscape forest cover influenced bird pollinator visits to Inga edulis trees in young restoration sites in Costa Rica. I. edulis trees were located in island plantings, where seedlings had been planted in patches, or in plantation plantings, where seedlings were planted to cover the restoration area. Sites were located in landscapes with scant (10–21% or moderate (35–76% forest cover. Trees with greater flower cover received more visits from pollinating birds; neither planting design nor landscape forest cover influenced the number of pollinator visits. Resident hummingbirds and a migratory bird species were the most frequent bird pollinators. Pollination in the early years following planting may not be as affected by details of restoration design as other ecological processes like seed dispersal. Future work to assess the quality of various pollinator species will be important in assessing this idea.

A Site Selection Model for a Straw-Based Power Generation Plant with CO2 Emissions

Directory of Open Access Journals (Sweden)

Hao Lv

2014-10-01

Full Text Available The decision on the location of a straw-based power generation plant has a great influence on the plant’s operation and performance. This study explores traditional theories for site selection. Using integer programming, the study optimizes the economic and carbon emission outcomes of straw-based power generation as two objectives, with the supply and demand of straw as constraints. It provides a multi-objective mixed-integer programming model to solve the site selection problem for a straw-based power generation plant. It then provides a case study to demonstrate the application of the model in the decision on the site selection for a straw-based power generation plant with a Chinese region. Finally, the paper discusses the result of the model in the context of the wider aspect of straw-based power generation.

Balancing effluent quality, economic cost and greenhouse gas emissions during the evaluation of (plant-wide) control/operational strategies in WWTPs

International Nuclear Information System (INIS)

Flores-Alsina, Xavier; Arnell, Magnus; Amerlinck, Youri; 2O Building, Emili Grahit 101, 17003 Girona (Spain))" data-affiliation=" (ICRA, Catalan Institute for Water Research, Scientific and Technological Park of the University of Girona, H2O Building, Emili Grahit 101, 17003 Girona (Spain))" >Corominas, Lluís; Gernaey, Krist V.; Guo, Lisha; Lindblom, Erik

2014-01-01

The objective of this paper was to show the potential additional insight that result from adding greenhouse gas (GHG) emissions to plant performance evaluation criteria, such as effluent quality (EQI) and operational cost (OCI) indices, when evaluating (plant-wide) control/operational strategies in wastewater treatment plants (WWTPs). The proposed GHG evaluation is based on a set of comprehensive dynamic models that estimate the most significant potential on-site and off-site sources of CO 2 , CH 4 and N 2 O. The study calculates and discusses the changes in EQI, OCI and the emission of GHGs as a consequence of varying the following four process variables: (i) the set point of aeration control in the activated sludge section; (ii) the removal efficiency of total suspended solids (TSS) in the primary clarifier; (iii) the temperature in the anaerobic digester; and (iv) the control of the flow of anaerobic digester supernatants coming from sludge treatment. Based upon the assumptions built into the model structures, simulation results highlight the potential undesirable effects of increased GHG production when carrying out local energy optimization of the aeration system in the activated sludge section and energy recovery from the AD. Although off-site CO 2 emissions may decrease, the effect is counterbalanced by increased N 2 O emissions, especially since N 2 O has a 300-fold stronger greenhouse effect than CO 2 . The reported results emphasize the importance and usefulness of using multiple evaluation criteria to compare and evaluate (plant-wide) control strategies in a WWTP for more informed operational decision making. - Graphical abstract: The 3-D representation of effluent quality (EQI), operational cost (OCI) and greenhouse gas emissions (GHG) during the evaluation of several (plant-wide) control/operational strategies: (1) modification of the DO set point, (2) modification of the primary clarifier TSS removal efficiency and (3) modification of the anaerobic

Balancing effluent quality, economic cost and greenhouse gas emissions during the evaluation of (plant-wide) control/operational strategies in WWTPs

Energy Technology Data Exchange (ETDEWEB)

Flores-Alsina, Xavier [Division of Industrial Electrical Engineering and Automation (IEA), Department of Measurement Technology and Industrial Electrical Engineering (MIE), Lund University, Box 118, SE-221 00 Lund (Sweden); Center for Process Engineering and Technology (PROCESS), Department of Chemical and Biochemical Engineering, Technical University of Denmark, Building 229, DK-2800 Kgs. Lyngby (Denmark); Arnell, Magnus [Division of Industrial Electrical Engineering and Automation (IEA), Department of Measurement Technology and Industrial Electrical Engineering (MIE), Lund University, Box 118, SE-221 00 Lund (Sweden); CIT Urban Water Management, Gjuterigatan 1D, SE-582 73 Linköping (Sweden); Amerlinck, Youri [BIOMATH, Department of Mathematical Modelling, Statistics and Bioinformatics, Ghent University, Coupure Links 653, B-9000 Ghent (Belgium); Corominas, Lluís [ICRA, Catalan Institute for Water Research, Scientific and Technological Park of the University of Girona, H_2O Building, Emili Grahit 101, 17003 Girona (Spain); Gernaey, Krist V. [Center for Process Engineering and Technology (PROCESS), Department of Chemical and Biochemical Engineering, Technical University of Denmark, Building 229, DK-2800 Kgs. Lyngby (Denmark); Guo, Lisha [ModelEAU, Département de génie civil et de génie des eaux, Université Laval, 1065 Avenue de la Médecine, Québec G1V 0A6, QC (Canada); Lindblom, Erik [Division of Industrial Electrical Engineering and Automation (IEA), Department of Measurement Technology and Industrial Electrical Engineering (MIE), Lund University, Box 118, SE-221 00 Lund (Sweden); Sweco Environment, Gjörwellsgatan 22, SE-100 26 Stockholm (Sweden); and others

2014-01-01

The objective of this paper was to show the potential additional insight that result from adding greenhouse gas (GHG) emissions to plant performance evaluation criteria, such as effluent quality (EQI) and operational cost (OCI) indices, when evaluating (plant-wide) control/operational strategies in wastewater treatment plants (WWTPs). The proposed GHG evaluation is based on a set of comprehensive dynamic models that estimate the most significant potential on-site and off-site sources of CO{sub 2}, CH{sub 4} and N{sub 2}O. The study calculates and discusses the changes in EQI, OCI and the emission of GHGs as a consequence of varying the following four process variables: (i) the set point of aeration control in the activated sludge section; (ii) the removal efficiency of total suspended solids (TSS) in the primary clarifier; (iii) the temperature in the anaerobic digester; and (iv) the control of the flow of anaerobic digester supernatants coming from sludge treatment. Based upon the assumptions built into the model structures, simulation results highlight the potential undesirable effects of increased GHG production when carrying out local energy optimization of the aeration system in the activated sludge section and energy recovery from the AD. Although off-site CO{sub 2} emissions may decrease, the effect is counterbalanced by increased N{sub 2}O emissions, especially since N{sub 2}O has a 300-fold stronger greenhouse effect than CO{sub 2}. The reported results emphasize the importance and usefulness of using multiple evaluation criteria to compare and evaluate (plant-wide) control strategies in a WWTP for more informed operational decision making. - Graphical abstract: The 3-D representation of effluent quality (EQI), operational cost (OCI) and greenhouse gas emissions (GHG) during the evaluation of several (plant-wide) control/operational strategies: (1) modification of the DO set point, (2) modification of the primary clarifier TSS removal efficiency and (3

Accident for natural gas well with hydrogen sulfide in relation to nuclear power plant siting

International Nuclear Information System (INIS)

Tan Chengjun; Shangguang Zhihong; Sha Xiangdong

2010-01-01

In order to make assessment to the potential impact from accident of natural gas wells with hydrogen sulfide on the habitability of main control room of nuclear power plant (NPP), several assumptions such as source terms of maximum credible accident, conservative atmospheric conditions and release characteristics were proposed in the paper, and the impact on the habitability of main control room was evaluated using toxicity thresholds recommended by foreign authority. Case results indicate that the method can provide the reference for the preliminary assessment to external human-induced events during the siting phrase of NPP. (authors)

Probabilistic performance assessments for evaluations of the Yucca Mountain site

International Nuclear Information System (INIS)

Rickertsen, L.D.; Noronha, C.J.

1992-01-01

Site suitability evaluations are conducted to determine if a repository system at a particular site will be able to meet the performance objectives for that system. Early evaluations to determine if the Yucca Mountain site is suitable for repository development have been made in the face of large uncertainties in site features and conditions. Because of these large uncertainties, the evaluations of the site have been qualitative in nature, focusing on the presence or absence of particular features or conditions thought to be important to performance, rather than on results of quantitative performance assessments. Such a qualitative approach was used in the recently completed evaluation of the Yucca Mountain site, the Early Site-Suitability Evaluation (ESSE). In spite of the qualitative approach, the ESSE was able to conclude that no disqualifying conditions are likely to be present at the site and that all of the geologic conditions that would qualify the site are likely to be met. At the same time, because of the qualitative nature of the approach used in the ESSE, the precise importance of the identified issues relative to performance could not be determined. Likewise, the importance of the issues relative to one another could not be evaluated, and, other than broad recommendations, specific priorities for future testing could not be set. The authors have conducted quantitative performance assessments for the Yucca Mountain site to address these issues

Independent technical evaluation and recommendations for contaminated groundwater at the department of energy office of legacy management Riverton processing site

Energy Technology Data Exchange (ETDEWEB)

Looney, Brain B. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Denham, Miles E. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Eddy-Dilek, Carol A. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

2014-04-01

The U.S. Department of Energy Office of Legacy Management (DOE-LM) manages the legacy contamination at the Riverton, WY, Processing Site – a former uranium milling site that operated from 1958 to 1963. The tailings and associated materials were removed in 1988-1989 and contaminants are currently flushing from the groundwater. DOE-LM commissioned an independent technical team to assess the status of the contaminant flushing, identify any issues or opportunities for DOE-LM, and provide key recommendations. The team applied a range of technical frameworks – spatial, temporal, hydrological and geochemical – in performing the evaluation. In each topic area, an in depth evaluation was performed using DOE-LM site data (e.g., chemical measurements in groundwater, surface water and soil, water levels, and historical records) along with information collected during the December 2013 site visit (e.g., plant type survey, geomorphology, and minerals that were observed, collected and evaluated).

Biological toxicity evaluation of Hanford Site waste grouts

International Nuclear Information System (INIS)

Rebagay, T.V. Dodd, D.A.; Voogd, J.A.

1992-10-01

Liquid wastes containing radioactive, hazardous, and regulated chemicals have been generated throughout the 50 years of operation of the Hanford Site of the US Department of Energy near Richland, Washington. These wastes are currently stored onsite in single- and double-shell carbon steel tanks. To effectively handle and treat these wastes, their degree of toxicity must be determined. The disposal of the low-level radioactive liquid portion of the wastes involves mixing the wastes with pozzolanic blends to form grout. Potential environmental hazards posed by grouts are largely unknown. Biological evaluation of grout toxicity is needed to provide information on the potential risks of animal and plant exposure to the grouts. The fish, rat, and Microtox toxicity tests described herein indicate that the grouts formed from Formulations I and 2 are nonhazardous and nondangerous. Using the Microtox solid-phase protocol, both soluble and insoluble organic and inorganic toxicants in the grouts can be detected. This protocol may be used for rapid screening of environmental pollutants and toxicants

Handbook for the planning, co-ordination and evaluation of emergency exercises in nuclear power plants

International Nuclear Information System (INIS)

Schmidtborn, I.; Bath, N.

1999-01-01

The efficiency of the on-site emergency organization in German nuclear power plants is tested regularly through emergency exercises. To achieve federal harmonization on a high level of quality a handbook for the planning, co-ordination and evaluation of such exercises has been developed in the frame of the regulatory investigation programme. In this handbook requirements are set out for emergency training. Key elements are a modular structure, rules to be observed and guidance for post-exercise evaluation. (orig.) [de

Development of a method to evaluate shared alternate AC power source effects in multi-unit nuclear power plants

International Nuclear Information System (INIS)

Jung, Woo Sik; Yang, Joon Eun

2003-07-01

In order to evaluate accurately a Station BlackOut (SBO) event frequency of a multi-unit nuclear power plant that has a shared Alternate AC (AAC) power source, an approach has been developed which accommodates the complex inter-unit behavior of the shared AAC power source under multi-unit Loss Of Offsite Power (LOOP) conditions. The approach is illustrated for two cases, 2 units and 4 units at a single site, and generalized for a multi-unit site. Furthermore, the SBO frequency of the first unit of the 2-unit site is quantified. The SBO frequency at a target unit of Probabilistic Safety Assessment (PSA) could be underestimated if the inter-unit dependency of the shared AAC power source is not properly modeled. The effect of the inter-unit behavior of the shared AAC power source on the SBO frequency is not negligible depending on the Common Cause Failure (CCF) characteristics among AC power sources. The methodology suggested in the present report is believed to be very useful in evaluating the SBO frequency and the core damage frequency resulting from the SBO event. This approach is also applicable to the probabilistic evaluation of the other shared systems in a multi-unit nuclear power plant

A Critical Evaluation of Waste Incineration Plants in Wuhan (China) Based on Site Selection, Environmental Influence, Public Health and Public Participation.

Science.gov (United States)

Hu, Hui; Li, Xiang; Nguyen, Anh Dung; Kavan, Philip

2015-07-08

With the rapid development of the waste incineration industry in China, top priority has been given to the problem of pollution caused by waste incineration. This study is the first attempt to assess all the waste incineration plants in Wuhan, the only national key city in central China, in terms of environmental impact, site selection, public health and public participation. By using a multi-criterion assessment model for economic, social, public health and environmental effects, this study indicates these incineration plants are established without much consideration of the local residents' health and environment. A location analysis is also applied and some influences of waste incineration plants are illustrated. This study further introduces a signaling game model to prove that public participation is a necessary condition for improving the environmental impact assessment and increasing total welfare of different interest groups in China. This study finally offers some corresponding recommendations for improving the environmental impact assessments of waste incineration projects.

A Critical Evaluation of Waste Incineration Plants in Wuhan (China Based on Site Selection, Environmental Influence, Public Health and Public Participation

Directory of Open Access Journals (Sweden)

Hui Hu

2015-07-01

Full Text Available With the rapid development of the waste incineration industry in China, top priority has been given to the problem of pollution caused by waste incineration. This study is the first attempt to assess all the waste incineration plants in Wuhan, the only national key city in central China, in terms of environmental impact, site selection, public health and public participation. By using a multi-criterion assessment model for economic, social, public health and environmental effects, this study indicates these incineration plants are established without much consideration of the local residents’ health and environment. A location analysis is also applied and some influences of waste incineration plants are illustrated. This study further introduces a signaling game model to prove that public participation is a necessary condition for improving the environmental impact assessment and increasing total welfare of different interest groups in China. This study finally offers some corresponding recommendations for improving the environmental impact assessments of waste incineration projects.

Preliminary Evaluation of Removing Used Nuclear Fuel from Shutdown Sites

Energy Technology Data Exchange (ETDEWEB)

Maheras, Steven J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Best, Ralph E. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Ross, Steven B. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Buxton, Kenneth A. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); England, Jeffery L. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); McConnell, Paul E. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Massaro, Lawrence M. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Jensen, Philip J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

2015-09-30

A preliminary evaluation of removing spent nuclear fuel (SNF) from 13 shutdown nuclear power reactor sites was conducted. At these shutdown sites the nuclear power reactors have been permanently shut down and the sites have been decommissioned or are undergoing decommissioning. The shutdown sites were Maine Yankee, Yankee Rowe, Connecticut Yankee, Humboldt Bay, Big Rock Point, Rancho Seco, Trojan, La Crosse, Zion, Crystal River, Kewaunee, San Onofre, and Vermont Yankee. The evaluation was divided into four components: (1) characterization of the SNF and greater-than-Class C low-level radioactive waste (GTCC waste) inventory, (2) a description of the on-site infrastructure and conditions relevant to transportation of SNF and GTCC waste, (3) an evaluation of the near-site transportation infrastructure and experience relevant to shipping transportation casks containing SNF and GTCC waste, including identification of gaps in information, and (4) an evaluation of the actions necessary to prepare for and remove SNF and GTCC waste. Every site was found to have at least one off-site transportation mode option for removing its SNF and GTCC waste; some have multiple options. Experience removing large components during reactor decommissioning provided an important source of information used to identify the transportation mode options for the sites. Especially important in conducting the evaluation were site visits, through which information was obtained that would not have been available otherwise. Extensive photographs taken during the site visits proved to be particularly useful in documenting the current conditions at or near the sites. It is expected that additional site visits will be conducted to add to the information presented in the evaluation.

Monitored Retrievable Storage facility site screening and evaluation report

Energy Technology Data Exchange (ETDEWEB)

none,

1985-05-01

The Nuclear Waste Policy Act of 1982 directs the Department of Energy to complete a detailed study of the need for and feasibility of, and to submit to the Congress a proposal for, the construction of one or more monitored retrievable storage facilities for high level radioactive waste and spent nuclear fuel.'' The Act directs that the proposal includes site specific designs. Further, the proposal is to include, for the first such facility, at least three alternative sites and at least five alternative combinations of such proposed sites and facility designs {hor ellipsis}'' as well as a recommendation of the combination among the alternatives that the Secretary deems preferable.'' An MRS Site Screening Task Force has been formed to help identify and evaluate potential MRS facility sites within a preferred region and with the application of a siting process and criteria developed by the DOE. The activities of the Task Force presented in this report, all site evaluations (sections 13 through 16) where the rationale for the site evaluations are presented, along with each evaluation and findings of the Task Force. This is Volume 3 of a three volume document. References are also included in this volume.